Radiation Dose Calculations for Library Geologic Media ... · Radiation Dose Calculations for Geologic Media Around Spent Fuel-Emplacement Holes in the Climax Granite, Nevada Test

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UCRI.53159

SAIT&MSSRadiation Dose Calculations for LIBRARY

Geologic Media Around Spent FuelEmplacement Holes in the Climax

Granite, Nevada Test Site

T. P. Wilcox

R. A. Van Konynenburg

May 27, 1981

I-

4.

DISCLAIMER

This document was prepared as an account of work sponsored by an agency of the United States Government.Neither the United States Government nor the University of California nor any of their employees, makesany warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com-pleteness, or usefulness of any information, apparatus, product, or process disclosed, or represents that itsuse would not infringe privately owned rights Reference herein to any specific commercial products, process.or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply itsendorsement, recommendation, or favoring by the United States Government or the University of California.The views and opinions of authors expressed herein do not necessarily state or reflect those of the UnitedStates Government thereof, and shall not be used for advertising or product endorsement purposes.

Work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore NationalLaboratory under Contract W-7405-Fng-48.

I

UCRL-53 159Distribution Category UC-70

Radiation Dose Calculations forGeologic Media Around Spent FuelEmplacement Holes in the Climax


T. P. Wilcox

R. A. Van Konynenburg

Manuscript date: May 27, 1981

LAWRENCE LIVERMORE LABORATORYIlLUniversity of California * Livermore, California * 94550

.P~2l

T&O' MSSU 13Rk4ARA-Y

Available from: National Technical Inrormation Service * U.S. Department of Commerce5285 Port Royal Road * Springfield, VA 221610 58.00 per copy * (Microfiche 53.50)

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CONTENTS

Abstract.................. IIntroduction ...............................................Characteristics of Radiation Source.2. ....................... . 2Geometry of Emplacement.. . . .................. . 5

Description of Materials.. . .................. . 5Calculational Approach.. . . .................. . 5Calculations.5. . ....... ........... . 5

Results.. ...................... . 9Uncertainty.9. ...................... .

Discussion.. ....................... 31Conclusions.. ....................... 32References.. . ............... 33Appendix A. Detailed Results. . ...................... 35

iii

Radiation Dose Calculations forGeologic Media Around Spent Fuel-Emplacement Holes in the Climax


ABSTRACT

Lawrence Livermore National Laboratory has emplaced I I spent nuclear-reactorfuel assemblies in the Climax granite at Nevada Test Site as part of the National Waste Ter-minal Storage Program. One of the objectives is to study radiation effects on the rock. Theneutron and gamma ray doses to the rock are being determined by calculation and measure-ment. This report discusses calculations performed using the MORSE-L Monte Carlo codeto determine dose rates and doses in the materials surrounding the spent fuel assemblies.The initial maximum dose rate to the granite is about 25 mGy/s (9 X 103 rad per hour),and the maximum dose integrated over five years is about 2.2 MGy (220 Mrad). The doserate is nearly constant over the central 2.44 m of the spent fuel assembly, and drops off ap-proximately exponentially with radius in the granite.

INTRODUCTION

As part of the National Waste TerminalStorage Program, Lawrence Livermore NationalLaboratory has emplaced 11 canisters of spentnuclear fuel from a commercial power reactor intoholes drilled in a granite formation. This project,called the Spent Fuel Test-Climax, is being carriedout at the Nevada Test Site.1 Plans call for the spentfuel to be left in place for three to five years whilemeasurements of temperatures, stresses, and dis-placements are made, and then to be removed toallow inspection of the holes and post-testing of thegranite. One of the objectives of the project is todetermine what effects the radiation from the spentfuel will have on the rock and backfill materials.Also of interest are radiation effects on the tem-perature profiles, corrosion of the steel liners, andradiolysis of water which may be present.

A plan has been written to study these radia-tion effects. 2 The plan calls for measurements ofthermoluminescence and changes in the rock's ther-mal, mechanical and structural properties. Con-

sideration is also being given to changes in ion-exchange properties.

In order to understand the results of thesemeasurements, as well as to relate them to otherwork, it is necessary to evaluate the radiation dosein the materials-around the emplacement holes. Thisis being accomplished by a combination of in situmeasurements and calculations. The measurementsare being carried out under a contract withE G & G Inc., of Goleta, Ca.3 They include gammaray dosimetry by optical absorption measurementsin7 LiF and neutron dosimetry by activation andsubsequent gamma ray counting of cobalt metalfoils. This report discusses the calculational part ofthe dose evaluation, which consists mainly ofMonte Carlo radiation transport calculations. Bycombining these two efforts, we can check theresults against each other, and we can obtain adetailed picture of the variation of dose with posi-tion, in the region of interest.

I

CHARACTERISTICS OF RADIATION SOURCE

The spent fuel used in the Spent FuelTest-Climax was manufactured by WestinghouseElectric Corporation and burned in Turkey PointUnit 3, which is a pressurized-water reactor ownedand operated by Florida Power and Light Com-pany. The fuel was discharged from the reactor onNovember 19, 1977. Three of the spent fuel assem-blies (DOI, D04, and D06) were given a detailed pre-test examination before emplacement. This ex-amination was conducted at the Battelle ColumbusLaboratories under the direction of the HanfordEngineering Development Laboratory (HEDL).4

Calorimetric measurements of decay heat were alsoperformed by HEDL on four assemblies, and theresults were in good agreement with calculations. 5

Eleven of the spent fuel assemblies were emplaced inthe Climax stock granite at Nevada Test Site duringApril and May, 1980.

Each fuel assembly6 consists of a bundle ofZircaloy-4 tubes in a 15 X 15 square array. Thetubes contain spent U0 2 fuel pellets. Each assemblyis about 4.09 m long overall, including the fuel tubesand the nozzles. The outside diameter of each fueledtube is 10.7 mm, and the wall thickness is 0.617 mm.The center-to-center spacing of the tubes is14.3 mm. The overall outside dimensions of the sec-tion containing spent fuel are 0.214 m square by3.66 m long.

In each assembly there are 20 control rod guidetubes and one instrument tube, distributed as shownin Fig. 1. These have an outside diameter of13.8 mm and a wall thickness of 0.43 mm. (Theguide tubes are actually smaller in diameter at thebottom to serve as dashpots, but this is not impor-tant for present purposes.) Originally, there were204 fueled tubes in each assembly. However, HEDLand Battelle4 removed four fueled tubes from eachof three assemblies (DOI, D04, and D06) andreplaced them with stainless steel dummy rods. Inaddition, the central instrument tube in these threeassemblies contains a package of material sampleswhose chemical compatibility under irradiation isbeing studied. Each assembly has seven spacer gridsto support the tubes.

The spent fuel emits both gamma rays andneutrons. The source strengths have been deter-mined by HEDL5 using the ORIGEN2 code.7 Forthe time period of interest, the gamma ray emissionis dominated by four nuclides (or nuclide pairs):

106Ru- 106Rh, 134CS, 137Cs- 137Ba, and 144Ce- 144Pr.The concentrations in gram-atoms calculated forassembly number D34, at 740 d since discharge,were supplied to us by Frank Schmittroth ofHEDL,8 and are shown in Table 1. The activities ofthese four emitters were then calculated for the agesof interest, using known half-lives.9 The values foran age of 2.45 y since discharge are also shown inTable 1. This age corresponds to May 1, 1980,which is approximately the average date of emplace-ment for the fuel assemblies. The actual emplace-ment dates for each assembly are shown in Table 2.Activities for later times were calculated by simpledecay.

The calculated neutron source strengths forassembly D34 were also supplied to us bySchmittroth.8 Neutron emission is dominated byspontaneous fission of 244Cm. There are also con-tributions from spontaneous fission of other ac-tinides and (alpha, n) reactions on the oxygen of theU02.10 At 740 d since discharge, the total emissionrate is 1.24 X 108 neutrons/s. Although the decayis less straightforward because of the in-growth of

0000000000000000000 000o0 E ED o000 @ 0000 @ @ 0009 @0O0 00 (@ 0 @ 00 00 e G O0 D 00 (@ 0oE e o O0 00000000000000000 Instrument tube3 Empty guide tube0 Tube containing U0 2

(only a few are shown)FIG. 1. Cross section of Westinghouse 15 X 15PWR fuel assembly.

2

I

TABLE 1. Significant gamma emitters in the spent fuel assemblies.

Concentration ActivityNucide at 740 d (gram-atoms). Half-Life at 245 y (Ci

106 Ru- 106 1 0.1575 366.5 d 4.18 X 104134 ca 0.1595 2062 y 2.40 x 104

137CS-137ia 3.202 30.17 y 3.76 x 104

4Ce,-144Pr 0.1516 284.5 d 4.77 X 104

TABLE 2. Characteristics of emplaced spent fuel assemblies.

Fuel Loading3 Burnupl2 Gamma Source Strength EmplacementAssembly No. (MTU) (MWD/MTU9' (relative to D34) - date (1980)

DOI 0.456902 28430 1.031 May 15D04 0.456655 28430 May 28D06 0.454893 28430 1.026 May 13D09 0.457078 27863 1.004 May I

D16 0.457722 27863 1.005 May 20

Dig 0.457360 27863 1.005 April 22

D34 0.455237 27863 1.000 April 25D35 0.454673 28430 1.026 May 6

D40 0.456091 28430 1.029 April 18D46 0456224 29430 1.029 April 29

D47 0.456373 28430 1.030 May 8

2Metric tons of uranium.

bMegawatt days per metric ton of uranium.

241Am, the total neutron emission decreases withtime over the period of interest.

The axial distribution of source strength can beestimated from the 137Cs gamma scans performedby HEDL and Battelle.4 (The two cesium isotopesare the dominant gamma emitters during the timeperiod of interest, and are also the most mobile, ow-ing to higher volatility.) Several of the gamma scanspresented in the HEDL report4 were hand fittedwith trapezoid-shaped curves and averaged. Theaveraged curve is shown in Fig. 2. As can be seen,the source strength is uniform over most of itslength, decreasing at each end. The decrease startsfurther from the end at the top because of thepresence of the control rods there during reactoroperation.

In the absence of information to the contrary,and in the knowledge that the reactor core is largecompared to the width of a fuel assembly, and thatthe control rods are well distributed, it was assumedthat the source strength does not vary significantlyacross the lateral dimensions of the fuel assemblies.

The gamma ray yields for the significantgamma emitters are shown in Table 3.9 Since mostof the neutrons result from spontaneous fission, itwas assumed that their spectrum is given by anequation of the form

N(E) = Ae 88Esinh n ,

where E is the energy (in MeV) and A is aconstant.l

3

M4..

C

.4.1

C0

0)U

40co*13

E

70

60

50

40

30

20

10

00 1 2 3 4

Distance from bottom of fuel element (m)FIG. 2. Axial gamma source distribution (dottedlines show the configuration used in the computersimulation).

Although the radiation source strengths of theII emplaced spent fuel assemblies are nearly thesame, there are small differences because of varia-tions in fuel loading and burnupl2,13(see Table 2).The removal of fuel tubes from near the centers ofthree of the assemblies, as mentioned above, shouldnot have a significant effect on the external fields,since little of the radiation from the interior tubesreaches the surface of an assembly, owing toself-shielding. We have therefore ignored the factthat some fuel tubes were missing.

Schmittroth et al.5 have calculated the heat out-put of the assemblies. Since most of the heat outputduring the time period of interest comes fromnuclides which are also the significant emitters ofgamma rays, 10 it appears that a satisfactory estimateof relative gamma ray source strengths can be ob-tained by use of relative heat output. We havetherefore taken ratios of their results for heat output(correcting them for actual fuel loading13). Therelative heat outputs of different assemblies varyslightly over time, because of different relativeamounts of the radionuclides, but over the timespan of interest, this variation amounts to only0.2%, and we have therefore ignored it. The relativegamma ray source strengths determined in this wayare shown in Table 2.

It is more difficult to estimate the relativeneutron source strengths, but since the dose fromneutrons to the granite turned out to be small com-pared to the dose from gamma rays, as pointed outbelow, we did not believe it necessary to estimatethese neutron source strengths.

A more important consideration in comparingthe actual doses to material around the II emplace-ment holes is the fact that they have different em-placement dates. However, this effect can becalculated only when the contributions of each ofthe radionuclides to the total dose is known; wediscuss this in more detail later.

TABLE 3. Gamma ray yields 9 of the significantgamma emitters in the spent fuel assemblies.

Nuclide Energy (MeV) Gammas/dLslntegradon

16R>,106}UE 0.5113 0.19

0.6163 0.0032

0.6221 0.0980.8738 0.0045

L.O0W 0.016

M.128 0.0042

1.562 00017

134Cs 0.4753 0.01465

0.5632 0.0833

0.5693 0.1543

0.6047 0.9756

0.7953 0.8544

0.8019 0.0873

1.0386 0.0100

1.1679 0.01803

1.3651 0.03041.4005 0.0003

37CS-137ft 0.6616 &0850

144 Ce-_1pr 0.0801 0.0113

0.1335 0.111

0.6965 0.0133

1.4891 0.0029

2.1356 0.007S

4

I

GEOMETRY OF EMPLACEMENT

Information about the emplacement geometrywas obtained from Refs. 14 and 15. The geometrydescribed in these publications is approximated bythat shown in Fig. 3. Note that the non-fueled partsof the assembly at top and bottom have been leftout, as have the spacer grids and assembly supportcage. The top plug geometry has been simplified.

Each spent fuel assembly was inserted into astainless steel canister 356 mm in outside diameter,with a wall thickness of 9.52 mm. The assembly wassupported by a thin stainless steel cage welded to theinside of the canister. Each canister was backfilledwith helium gas and welded shut.

The canisters were lowered into vertical holesdrilled into the floor of a drift mined in the quartzmonzonite unit of the Climax Stock, located at theNevada Test Site. The holes were lined with carbonsteel liners prior to insertion of the canisters. Theseliners were grouted in position at top and bottom.The liners have an outside diameter of 457 mm anda 6.35 mm wall thickness. The holes in the granitehave a diameter of 610 mm. A large steel shield plugcovers each canister. The grouting was limited toregions above and below the active section of thespent fuel.

The space between the canister and liner isfilled with air. The region between the liner and thegranite was initially filled with air. However, it wasrecognized that water may seep into this regionthrough cracks in the granite. Also, it is possible toremove some of the spent fuel after three years andbackfill this region with an ion exchange materialsuch as bentonite clay. Accordingly, it is of interestto calculate doses for the four cases of air, water,compacted bentonite, and a sand-bentonite mixturein this region.

Small holes were drilled into the granite nearthe emplacement holes for insertion of instrumenta-tion and dosimeters.

Figure 4 shows the geometry used forcalculational purposes.

DESCRIPTION OF MATERIALS

The parameters of importance for calculationof radiation transport are density and chemicalcomposition. The values used are shown in Table 4.It was estimated that 3.0% of the uranium in the fuelhad been converted to fission products, with an

average atomic number of 116.10 The density ofU02 was taken to be the "planar smear density"with the "dish smeared in." 12 That means that thedensity was calculated by dividing the mass of theU02 by the entire inside volume of the claddingtubes. (The "dish" refers to the concave surfacemachined into the ends of the fuel pellets to allowfor expansion.) The grout composition was approx-imated from handbook information.2 0 The ben-tonite backfill materials are those used in theSwedish KBS study.21 ' 22

CALCULATIONAL APPROACH

At first glance, it may appear that the dose dis-tribution could be determined relatively easily byhand calculation. Further consideration, however,indicates several complicating factors:

* Each fuel assembly contains enoughuranium to produce considerable self-absorption,and several scattering collisions occur before theaverage gamma ray reaches the granite.

* The nonuniform structure of the fuel ele-ment, with both the fuel pins and void gaps betweenthem, complicates the transport of radiation out ofthe element itself. Because of this structure the fluxat the surface of the element will vary with angularposition, and this variation will greatly affect thecalculated fluxes in the surrounding materials.

* This same structure of the fuel element willcause streaming end effects at both the top and bot-tom of the element.

* The fuel assembly emits gamma rays andneutrons over considerable energy ranges. Thetransmission properties of the media vary greatlyover these energy ranges.

* Many of the desired results are the fluxes atinterfaces between different materials. The handcalculations are not accurate for such interfaces.

For all these reasons, we decided to use aMonte Carlo calculational approach. Radiationtransport calculations for a shipping cask24 and fora transfer cask, surface storage cask, and dry well25

for these fuel assemblies have been reported.

CALCULATIONS

Calculations were performed on a CDC 7600computer using the MORSE-L Monte Carlo code.26

S

I

FIG, 3. Approximate geometry of spent fuel emplacement. Calculations assumed voids rather than air or heliumin the actual case; this substitution is indicated by the "void" in parentheses in the figure.

6

f . t . :: h

3'- 10r-

81-2541 I III I I

3 i34 i 9 57 65 73 81 89 97

1 I I I I I I I I I21-6 .. .. .

.. ~~~~ .. - ..

I '1 113 i

26 I 429 34L1 UII3 6 74 L I,

4 -

1-

2 _-

"I O

V

0 _

8 14 2 35 5 69 67 75 83 .91 9

20 35 451 1 TH9 I9 15 7 21 36 52 60 68 76 84 92 IC

HI HI <H2'9 451< <10 16 37 53 61 69 77 85 93 iC

1 17 23 1 54 62 70 78 86

.. I T I I I I I I I . . .

-2 _-

-1 --4

-66 1L

1118 2

11I 1 3 1 47

rI 71 I5 6:

I I371 79

I II 7 5 1

4-I--4-I-4-4-4-4-4-4 I I I I-2 _- II

321401 64 752 80 88 96

1 I 56 I 1 I I IIc

-8I I I I I I I 1. I I

0

3 L9 12 14 16

I nches

I

18 20 22 24 26 30 32

I I I

0 0.3 0.6

Meters

FIG. 4. Boundaries (cf. Tables A1-AIS) established for calculation. Note that boundaries 7 through 13 arelocated on the outside surfaces of the canister and liner.

Gamma cross sections used were those of the stan-dard LLNL L-Division 35 group gamma library.27

With this library, the code follows the history ofphotons through successive scatters until theirenergy falls below 150 keV, when they are assumedto be totally absorbed. The general problem

geometry is shown in Fig. 3. The fuel elementassembly was modeled exactly as described in theprevious discussion, except that the empty tubeswere considered to have the same dimensions as theloaded tubes. The radiation source was consideredto consist of a uniform volume source in each fueled

7

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TABLE 4. Density and composition of materials subject to irradiation.

Analysis

Material Density (g/em3) Element WI%

L02 0.8W2 12 X 10.9616 U

0

Zircaloy-417

304L Stainless

Steel'83 19

Carbon Steel

Grout2 0

Water

Compacted

bentonite with

10% Water2 l

Sand/bentonite (85%/15% dry)

plus 10% water2 2

6.60 Zr

Sn

Fe

Cr

7.90 Fe

Cr,Ni

Mn

Si

7.3719 Fe

2.0 0

Si

Ca

Fe

Al

Mg

88&

11.9

98.24

1.45

0.21

0.10

68.0

19.0

10.0

2.0

1.0

100.0

42.5

40.0

15.0

1.0

1.0

0.5

8.9

11.1

58.0

28.0

10.0

2.3

1.7

57.0

40.0

I S

0.3

1.2

1.0 0H

2.1 0

Si

Al

Fe

H

2.17 0

Si

Al

Fe

H

Granite (Climax

Stock quartz

monzonite)23

2.68 0

Si

Al

Fe

Ca

Na

K

52.0

37.0

7.0

1.0

1.0

1.0

1.0

8

I

C_

pin, with the axial intensity distribution shown inFig. 2. Fluxes were obtained from the Monte Carlorandom-walk parameters by using the boundary-crossing technique.26 Figure 4 indicates the boun-daries established ..in the problem's geometrydescription.. Note that these are 610 mm-high seg-ments on the outside of the fuel element, the outsideof the stainless steel and iron containers, the innersurface of the granite, and various calculational sur-faces within the granite. It should be noted that theboundary-crossing technique yields the averagevalue of the flux over the area being used.

Separate gamma calculations were made foreach of the four radionuclides of interest. The

results were then summed (taking into account theappropriate initial activity of the nuclides and theirradioactive decay), to produce results at varioustimes after emplacement. Integrated results werealso obtained for the first three years, the followingtwo years, and the complete five-year period.

After the series of problems was run with thegamma sources, the neutron source was modeled,and coupled neutron-gamma MORSE-L problemswere run to determine neutron dose rates and secon-dary gamma dose rates.

The previously described calculations wererepeated four times with four different materials inthe liner-granite gap.

RESULTS

In all cases, out to a radius of 762 mm, theneutron dose was negligible compared to thegamma ray dose. Within the statistical uncertaintyof the calculation, the dose was independent of ver-tical location over the central 2.44 m of the fuelassembly. Accordingly, the results for the central2.44 m were averaged to produce a single result withreduced statistical variation.

The absorbed dose rate results as a function ofradius for the central 2.44 m of the fuel assembly aregiven in Tables 5 through 12 at one-year intervals.The integrated absorbed doses for both granite andLiF as a function of radius for the three timeperiods are given in Tables 13 through 20. Figures 5through 8 show plots of the data of Tables 5through 20, outside the 229 mm radius.

The detailed results are given in Appendix A.Tables A-1 through A-8 show the granite and LiFabsorbed dose rate results for each calculationalboundary surface at one-year intervals using thefour different liner-granite gap materials. TablesA-9 through A-16 show the integrated absorbeddoses for all the cases, using the three time periodsof interest.

UNCERTAINTY

There are several sources of uncertainty inthese results. A complete error analysis would re-quire repeating the Monte Carlo calculations withdifferent sets of input parameters in order to deter-mine the sensitivity of the results to each pertinentparameter. We do not believe such an approach is

warranted in this case. However, an indication ofthe magnitude of the overall uncertainty can begained from an examination of each source.

The first uncertainty is in the concentrations ofthe radionuclides present in the assembly. Althoughwe do not have a direct evaluation of their uncer-tainties, we can get some information from the workof Schmittroth et al.,5 from which the data came.These authors calculated the uncertainty (la) intheir estimate of decay heat to be 18.6%, takinginto account uncertainties in reactor power, irradia-tion time, burnup, nuclear data, and calculationalmethods. For assembly number D34, theirmeasured decay heat value was 5.8% lower thantheir calculated value. The uncertainty in themeasurement was estimated at 45%. As mentionedabove, the four principal gamma emitters con-sidered in our calculation account for most of themeasured heat output (about 80%). Therefore, theuncertainties in the nuclide concentrations used forour calculation are probably comparable to the un-certainty in the calculation of decay heat, that is, nogreater than about 10%.

The next source of uncertainty is the calcula-tion of gamma ray source strengths from the con-centrations. The uncertainty in the nuclear dataused for this calculation is about ±5% in the highestcase, but generally 4 1% or less.

Neglect of all but four nuclides (or nuclide-pairs) tends to cause the calculation to un-derestimate the actual doses. The magnitude of thiserror can also be estimated from the work ofSchmittroth et al.5 As noted, 80% of the measureddecay heat comes from the nuclides considered in

9

TAIBLE 5. The calculated absorbed dose rate (rad/h to GRANITE) at several calculational surfaces and atvarious elapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft)of the fuel assembly. The liner/granite gap was assumed to be VOID.

RAD PER HOUR

2.45 YR. 3.46 YR._ _ _ _ _ _ _ _ - - - - - - - -

a

OUTSIDE ELEMENT

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHII1 GRANITE

13 INCH RADIUS

14 INCH RADIUS

15 INCH RADIUS

16 INCH RADIUS

18 INCH RADIUS

20 INCH RADIUS

22 INCH RADIUS

24 INCH RADIUS

26 INCH RADIUS

30 INCH RADIUS

5.70E+04

2.04E+04

1 20E +04

9.42E+03

6.68E+03

4.20E+03

2.79E+03

1.82E+03

7.76E+02

3.24E+02

1.42E+02

6.03E+01

2.75E+01

S.44E+00

4.05E+04

1.44E+04

8.40E +03

6.63E+03

4. 69E+03

2.92E403

1. 93E+03

1.24E+03

5.16E+02

2.09E+02

8.86E+01

3.58E+01

1.60E+01

2.69E+00

3.53E+03

2. 19E+03

1.43E+03

9. 19E+02

3.72E+02

1. 48E +02

6.09E+01

2.35E+01

1.04E+01

1 .47E+00

2. SlE 03

1.73E403

1. 13E+03

7.22E4092

2.87E+02

1. 13E452

4.56E401

1.68E 401

7.52E800

9.03E-01

2.34E+03

1.44E+03

9.31E +02

5. 95E +02

2. 34E+02

9.21E+01

3.64E+01

1.30E+01

5.89E+00

6.26E-01

4.45 YR. 5.45 YR. 6.45 YR.

3.08E+04 2.46E+04 2.06E+04

1.09E+04 8.68E+03 7.23E+03

6.33E+03 5.04E+03 4.20E+03

5.00E+03 3.98E+03 3.32E+03

7.45 YR.

1. 77E+04

6.23E+03

3.62E+03

2.85E+03

2.01E +03

1.24E+03

7.96E+,02

5.09E+402

1.90E+02

7.8 1E+01

3.05E+01

1.06E+01

4.90E+00

4.78E-01

8.00 YR.________

1.66E+04

5.82E+03

3.38E+03

2.67E+03

1.87E+03

1 . 15E+03

7.41E+02

4.74E+02

1 .83E+02

7.25E+01

2.82E+01

9.63E+00

4.52E+00

4.27E-01

TABLE 6. The calculated absorbed dose rate (rad/h to GRANITE) at several calculational surfaces and atvarious elapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft)of the fuel assembly. The liner/granite gap was assumed to be filled with WATER.

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.

OUTSIDE ELEMENT. 5.66E+04 4.03E+04 3.06E+04 2.46F+04 2.06E+04 1.78E+04 1.67E+04

OUTSIDE SS CANISTER 2.03E+04 1.44E+04 1.09E+04 8.66E+03 7.23E+03 6.24E+03 5.83E+03

OUTSIDE IRON LINER 1.25E+04 8.80E+03 6.66E+03 5.32E+03 4.45E+03 3.84E+03 3.59E+03

SURFACE OF GRANITE 6.45E+03 4.51E+03 3.39E+03 2.69E+03 2.23E+03 1.91E+03 1.78E+03

WITHIN GRANITE

13 INCH RADIUS 4.0UE+03 2.83E+03 2.11E+03 1.67E+03 1.38E+03 1.19E+03 l.llE+03

14 INCH RADIUS 2.55E+03 1.81E+03 1.37E+03 1.10E+03 9.17E+02 7.93E+02 7.42E+02








3.0 INCH RADIUS 3.52E+00 1.64E+00 8.29E-01 4.64E-01 2.93E-01 2.08E-01 1.80E-01

TABLE 7. The calculated absorbed dose rate (rad/h to GRANITE) at several calculational surfaces and atvarious elapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 mk (8 ft)of the fuel assembly. The liner/granite gap was assumed to be filled with COMPACTED BENTONITE.

RAD PER HOUR

t.J

OUTSIDE ELEMENT

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHIN GRANITE

13 INCH RADIUS

14 INCH RADIUS

16 INCH RADIUS

16 INCH RADIUS

18 INCH RADIUS

20 INCH RADIUS

22 INCH RADIUS

24 INCH RADIUS

26 INCH RADIUS

30 INCH RADIUS

2.45 YR.

5.70E+04

2.86E 404

1.28E+04

4.25E+03

2.73E+03

1. 71E +03

1. 1 IE+03

7.29E402

2.91E+02

1.25E+02

5.77E+01

2.49E"01

1.38E+01

2.40E+00

3.45 YR.

4.06E+04

1.45E+04

8.99E +03

2.96E+03

1. 88E+03

1. 16E+03'

7.46E+02

4.86E+02

1.88E+02

7.74E+81

3.45E+01

1.42E+01

7. 84E+00

1. 14E+00

I . 4HE +03

8.58E+02

S. 45E .02

3.52E402

1.33E+02

5S. 31E +01

2.28E401

9 .08E.00

4.89E+99

5.B8E-01

1. 10E+03

6.74E+02

4.24E+02

2.7ZE+02

1.01E+02

3.96E+01

1.65E+01

6.40E+00

3.33E+00

3.31E-01

9.12E+02

5.56E+02

3.48E+02

2.22E+02

8.20E+01

3.16E+01

1.29Et01

4.91E+00

2.44E+00

2.05E-01

4.45 YR. 5.45 YR. 6.45 YR.

3.B8E+04 2.47E+04 2.07E+04

1.10E+04 8.76E+03 7.30E+03

6.77E+03 5.39E+03 4.49E+03

2.21E+03 1.75E+03 1.46E+03

7.45 YR.

1 .79E+04

6.29E+53

3.87E+03

1.25E+03

7.82E+02

4.76E+02

2.96E+02

1.88E+02

6.93E+01

2.64E+01

1.06E+01

4.0E+400

1 .9BE+00

1.39E-01

7.28E+02

4.43E+62

2.75E 402

1. 74E+02

6.42E.01

2.44E+01

9. 67E400

3.665E 50

1 .69E*09

1 . 16E-01

8.00 YR.________

1.67E+04

5.87E+03

3.61E+03

1. 17E+03

;

TABLE 8. The calculated absorbed dose rate (rad/h to GRANITE) at several calculattoml surfaces and atvarious elapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft)of the fuel assembly. The liner/granite gap was assumed to be filled with SAND/BENTON1TE.

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.53 YR.

OUTSIDE ELEMENT 5.66E+04 4.03E+04 3.06E+04 2.46E+04 2.06E+04 1.78E+04 1.67E+54

OUTSIDE'SS'CANISTER 2.04E+04 1.44E+04 1.09E+04 8.72E+J3 7.27E+03 6.27E+03 5.86E+03

OUTSIDE IRON LINER 1.27E+04 8.95E+03 6.75E+03 5.38E+03 4.48E+03 3.86E+83 3.61E+J3

SURFACE OF GRANITE 4.07E+03 2.84E+03 2.'13E+03 1.69E+03 1.41E+83 1.21E+83 1.13E+03

WITHIN GRANITE



15 INCH RADIUS 1.05E+03 7.36E+82 5.17E+02 4.04E+g2 3.33E+02 2.85E+02 2.66E+02


18 INCH RADIUS 2.98E+02 1.92E+02 1.35E+02 1.03E+02 8.28E+01 6.98E+4Z 6.46E+01


22 INCH RADIUS 5.46E+01 3.30E+0l 2.21E+01 1.62E+01 1.28E+01 1.06E+01 9.75E+00

24 INCH RADIUS 2.51E+01 1.43E+01 9.04E+00 6.37E+00 4.90E+00 4.52EiZZ 3.68E+00

26 INCH RADIUS 1.22E+01 6.58E+00 3.96E+00 2.66E+00 1.98E+00 1.58Ee00 1.43E+00

33 INCH RADIUS 2.73E+00 1.33E+00 7.IBE-01 4.28E-01 2.93E-01 2.23E-01 1.99E-01

TABLE 9. The calculated absorbed dose rate (rad/h to LiF) at several calculational surfaces and at variouselapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft) of thefuel assembly. The liner/granite gap was assumed to be VOID.

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.02 YR.…_______ ------ -- -------- --- ----- --- ----- -------- --- -----

OUTSIDE ELEMENT

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHIN GRANITE

13 INCH RADIUS

14 INCH RADIUS

15

16

18

20

22

24

26

30

INCH

INCH

INCH

INCH

INCH

INCH

INCH

INCH

RADIUS

RADIUS

RADIUS

RADIUS

RADIUS

RADIUS

RADIUS

RADIUS

5.28E+04

l.88E+40

1 . 1OE 404

8.67E 403

6. 14E403

3.86E403

2. 56E +03

1 .67E.03

7. 1E402

2. 97E402

1.32E402

5.59E401

2.54E401

5 .97E.00

3.76E+04

1.33E+04

7.74E+03

6. 10E+03

4.31E+03

2.68E+03

1.77E+03

1. 14E+03

4.72E+02

1.92E+02

8.25E+01

3.33E+01

1.48E+01

2.54E+00

2.85E+94 2.28E+04

1.00E404 S.ZlEe03

5.83E.03 4.65E403

4.69E403 3.66E403

3.24E+03

2.01E +03

1.31E+03

8.42E+02

3.41E+02

1.36E+02

5.70E+01

2.20E+01

9.67E+00

1.42E+40

2.58E+03

1.59E+03

1.03E+03

6.61E+02

2.63E+02

1.04E+02

4.29E+01

1.59E+01

7.00E+00

8.93E-01

2.14E4'03 1.84E+93 1.72E+03

1.32E+03

8.53E+02

S.45E+02

2. 14E+02

8.44E+01

3.45E+01

1.23E+01

5.51E+00

6.37E-01

1 * 13E403

7. 30E +02

4.66E.02

1 .81E402

7. 16E401

2.90E*01

1 .8lE.01

4.59E400

4.99E-81

1 .06E+03

6.79E.02

4.34E+02

1 .68E+02

6.65E+0I

2.69E+01

9. 22E+00

4.25E900

4.52E-91

1.91E+04

6.68E+03

3.87E+03

3.05E+03

1. 65E+04

6.76E+03

3.34E+03

2.62E+93

1 .54E+04

5.38Ee03

3.12E+03

2.45E.03

;

TABLE 10. The calculated absorbed dose rate (rad/h to LIF) at several calculational surfaces and at variouselapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft) of the

fuel assembly. The liner/granite gap was assumed to be filled with WATER.

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR.…_______ -------- -------- --------6.45 YR. 7.45 YR. 8.00 YR.________ -------- --------

OUTSIDE ELEMENT

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHIN GRANITE

13 INCH RADIUS

14 INCH RADIUS

15 INCH RADIUS

16 INCH RADIUS

18 INCH RADIUS

20 INCH RADIUS

22 INCH RADIUS

5.24E+J4

1.88E.04

1. 15E+04

5.92E+03

3.56E+03

2.34E+03

1 .58E+03

1 .0IE*03

4.48E+02

1 .81E+02

7.48E+01

3.28E+01

1.65E+01

3.73E+04

1.33E+04

8.1 IE+03

4.14E+03

2.42E+03

1.66E+03

1.08E+03

6.76E+02

2.94E+02

1. 15E+02

4.46E+01

1.85E+01

8.78E+00

2.84E+84

1 .OE +04

6. 13E.03

3. liE .03

1 .76E+83

1.26E'03-

7.96E+82

4.92E402

2. 11IE+82

7.96E+81

2.96E 401

1I* 17E.01

5. 2HE e0

2.28E+04

B .00E+03

4. 9AE+03

2.47E+03

1 .36E+03

1 .I1E+03

6.25E+02

3.82E40f2

1 .63E+02

5. 99E .01

2. 16E+H1

8.25E+00

3.45E+00

1 .91 E,*04

6.68E.03

4.09E.03

2. 05 E .03

1 .1E.03

8. 4#E+62

5. 16Ee02

3.13E.02

I1.33E'02

4. 80E +01

1. .70E.01

6. 40E +00

2.54E+00

1.65E+04

5.76E+03

3.53E+03

1.76E+03

9.24E+02

7.26E+02

4.42E+02

2.66E+02

1. 13E+02

4.03E+01

1.42E+01

5. 30E +00

2.02E+00

1.55E+04

5.38E+03

3.31E+03

1.64E*03

8.53E+02

6.79E+02

4.12E+02

2.47E+02

1.05E+02

3.73E+01

1.31E+01

4. 89E+00

1. 83E+00

ZA

24

26

INCH

INCH

RADIUS

RADIUS

30 INCH RADIUS 3.14E+00 1.44E+00 7.13E-01 3.94E-01 2.51E-01 1.81E-01 1.59E-01

TABLE II. The calculated absorbed dose rate (rad/h to LiF) at several calculational surfaces and at variouselapsed times since discharge of fuel from reactor. The values are averages over the central 2.44 m (8 ft) of thefuel assembly. The liner/granite gap was assumed to be filled with COMPACTED BENTONITE.

RAD PER HOUR

OUTSIDE ELEMENT

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHIN GRANITE

13 INCH RADIUS

14 INCH RADIUS

15 INCH RADIUS

16 INCH RADIUS

18 INCH RADIUS

20 INCH RADIUS

22 INCH RADIUS

24 INCH RADIUS

26 INCH RADIUS

30 INCH RADIUS

2.45 YR.

5.29E+04

1 .90E+04

1. 18E+04

3.90E+03

2.50E+03

1. 56E +03

1 .02E+03

6.68E+02

2.67E +02

1 .15E+02

5.40Et01

2.30E+01

1.28E+01

2.26E+00

3.45 YR.

3.76E+04

1.34E+04

8.28E+03

2.71E+03

1.72E+03

1.07E+03

6.83E+02

4.45E+0?

1.72E+02

7.14E+01

3.27E+01

1.32E+01

7.26E+00

1. 10E+00

4.45 YR. 5.45 YR. 6.45 YR.

2.86E+04 2.29E+04 1.92E+04

1.01E+04 8.09E+03 6.74E+03

6.24E+03 4.97E+03 4.14E+03

2.03E+03 1.61E+03 1.33E+03

1.28E+03

7.86E+02

4.99E+02

3.22E+02

1.22E+02

4.91E+01

2. 19E+01

8.42E+00

4.55E+00

5.8SE-01

1.01E+03

6.17E.02

3.88E+02

2.49E+02

9.27E+01

3.67E+01

1.61E+01

5.96E+00

3.12E+00

3.46E-01

8.35E+02

5.09E+02

3. 18E+02

2.03E+02

7.50E+01

2.94E+01

1.27E+01

4.59E+00

2.30E+00

2.30E-01

7.45 YR.

1.66E+04

5.SZE+03

3.56E+03

1. 15E+03

7.16E+02

4.35E+02

2.71E+02

1.72E+02

6.34E+01

2.46E+01

1.06E+01

3.75E+90

1. 80E+00

1.67E-01

8.00 YR.________

1.55E+04

5.42E+03

3.33E+03

1.07E+03

6.67E+02

4.05E+02

2.52E+02

1.59E+02

5.88E+01

2.28E+01

9.73E+00

3.43E+00

1.61E+00

1.45E-01

TABLE 12. The calculated absorbed dose rate (rad/h to LIF) at several calculational surfaces and at variouselapsed times since discharge of fuel from meactor. The values are averages over the central 2.44 m (8 ft) of thefuel assembly. The liner/granite gap was assumed to be Milled with SAND/BENTONITL

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.

OUTSIDE ELEMENT 5.24E+04 3.73E+04 2.84E+J4 2.28E+04 1.91E+04 1.65E+04 1.55E+04

OUTSIDE SS CANISTER 1.89E+04 1.33E+04 1.h1E+04 8.05E+03 6.71E+03 5.79E+03 5.41E+03

OUTSIDE IRON LINER 1.17E+04 8.24E+83 6.22E+03 4.96E+03 4.13E+03 3.56E+03 3.32E+03

SURFACE OF GRANITE 3.74E+J3 2.60E.03 1.95E+03 1.55E+03 1.29E+03 l.llE+03 1.04E+J3

WITHIN GRANITE

13 INCH RADIUS 2.4JE+03 1.65E+03 1.23E+03 9.72E+02 8.06E+02 6.92E+02 6.46E402

14 INCH RADIUS 1.51E+03 1.03E+03 7.61E+82 5.99E+02 4.95Ee02 4.24E+JZ 3.96E+J2

15 INCH RADIUS 9.62E+02 6.47E+02 4.73E+02 3.70E+02 3.05E+02 2.61E+J2 2.43E+J2


18 INCH RADIUS 2.73E+02 1.75E+02 1.24E+02 9.38E+51 7.57E+J1 6.37E+O1 5.90E+O1


22 INCH RADIUS 5.00E+01 3.02E+01 2.J2E+01 1.48E+01 1.17E+01 9.67E+08 8.90E+J0

24 INCH RADIUS 2.30Et01 1.31E+01 8.28E+0J 5.83E+0J 4.48E+09 3.67E+00 3.36E+00

26 INCH RADIUS 1.12E+01 6.55E+00 3.64E+00 2.44E.0U 1.81E+00 1.44E+J0 1.31E+J0

30 INCH RADIUS 2.51E+00 1.22E+00 6.51E-01 3.92E-J1 2.67E-01 2.J3E-01 1.81E-01

I

TABLE 13. The calculated absorbed dose (rad toGRANITE) at several calculational surfaces and overthree time periods after discharge of fuel from reac-tor. The values are averages over the central 2.44 m(8 ft) of the fuel assembly. The liner/granite gap wasassumed to be VOID.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

OUTSIDE ELEMENTS 9.67E+08 1.33E+09 3.61E+08

OUTSIDE SS CANISTER 3.44E+09 4.71E+09 1.27E+08

OUTSIDE IRON LINER 2.ZZE+08 2.74E+08 7.38E+07

SURFACE OF GRANITE 1.58E+08 2.16E+08 5.83E+57

WITHIN GRANITE

13 INCH RADIUS 1.12E+08 1.53E+08 4.11E+37

14 INCH RADIUS 6.96E+Z7 9.49E+07 2.53E+07

15 INCH RADIUS 4.58E+07 6.22E+07 1.64E+07

16 INCH RADIUS 2.96E+07 4.00E+07 1.05E+07

18 INCH RADIUS 1.22E+07 1.63E+07 4.11E+06

20 INCH RADIUS 4.94E+06 6.56E+06 1.62E+06

22 INCH RADIUS 2.08E+06 2.72E+06 6.43E+05

24 INCH RADIUS S.34E+05 1.06E+06 2.30E+05

26 INCH RADIUS 3.74E+05 4.78E+05 1.04E+05

30 INCH RADIUS 6.16E+04 7.28E+04 1.13E+04

18

TABLE 14. The calculated absorbed dose (rad toGRANITE) at several calculational surfaces and overthree time periods after discharge of fuel from reac-thr. The values are averages over the central 2A4 m(8 ft) of the fuel assembly. The liner/granite gap wasassumed to be filled with WATER.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

OUTSIDE ELEMENTS 9.62E+08 1.32E.09 3.62E+08

OUTSIDE SS CANISTER 3.42E.88 4.70E408 1.27E+08

OUTSIDE IRON LINER 2.11E+08 2.86E+68 7.81E+07

SURFACE OF GRANITE 1.07Ei08 1.47E+08 3.92E+07

WITHIN GRANITE

13 INCH RADIUS 6.73E+07 9.16E+07 2.43E.07

14 INCH RADIUS 4.32E+07 5.93E+07 1.61E407

15 INCH RADIUS 2.79E+07 3.79E+07 9.92E.06

16 INCH RADIUS 1.75Ei07 2.35E+67 6.01E.06

18 INCH RADIUS 7.59E.06 1.JlE'07 2.56Ee06

20 INCH RADIUS 2.51Ee06 3.31E+06 8.06E.05

22 INCH RADIUS 1.14Ee06 1.47E+66 3.30E+05

24 INCH RADIUS 4.69E+05 5.93E.05 1.24E+05

26 INCH RADIUS 2.21E+05 2.70E405 4.96E+04

30 INCH RADIUS 3.73E+04 4.26E404 5.35E+03

19

J

TABLE 15. The calculated absorbed dose (rad toGRANITE) at several calculational surfaces and overthree time periods after discharge of fuel from reac-tor. The values are averages over the central 2.44 m(8 ft) of the fuel assembly. The liner/granite gap wasassumed to be filled with COMPACTED BEN-TONITE.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR…___________ ------------ ------------

OUTSIDE ELEMENTS 9.69E+0S 1.33E+09 3.63E+08


OUTSIDE IRON LINER 2.14E+Z8 2.93E+08 7.90E+07


WITHIN GRANITE

13 INCH RADIUS 4.47E+07 6.08E+07 1.60E+07

14 INCH RADIUS 2.76E+07 3.74E+07 9.79E+06

15 INCH RADIUS 1.77E+07 2.38E+07 6.12E+06

16 INCH RADIUS 1.15E+07 1.54E+07 3.90E+.6

18 INCH RADIUS 4.43E+Z6 5.87E+06 1.44E+Z6

20 INCH RADIUS 1.82E+06 2.37E+06 5.57E+55

22 INCH RADIUS 8.05E+05 1.53E+56 2.27E+Z5

24 INCH RADIUS 3.31E+55 4.18E+05 0.7ZE+04

26 INCH RADIUS 1.81E+05 2.24E+05 4.33E+Z4

30 INCH RADIUS 2.59E+04 2.96E+04 3.73E+Z3

20

I

TABLE 16. The calculated absorbed dose (rad toGRiANhE) at several calculational surfaces and overthree time periods after discharge of fuel from reac-tor. ITe values are averages over the central 2.44 m(8 ft) of the fuel assembly. The liner/granite gap wasassumed to be filled with SAND/BENTONITE.

RADS

2.45-5.45 YR 2.45-7.45 YR 6.45-7.45 YR-___________ ------------ -----

OUTSIDE ELEMENTS 9.62E4I8 1.32E+59 3.62E+68




UITHIN GRANITE

13 INCH RADIUS 4.29Ee07 5.84E.07 1.55E107

14 INCH RADIUS 2.68E.17 3.63E.57 9.51E+96

15 INCH RADIUS 1.68E.17 2.26E+07 5.86E+06

16 INCH RADIUS 1.06E.57 1.42E+07 3.60E.E6

18 INCH RADIUS 4.52E'06 5.98E+06 1.46E406

2U INCH RADIUS 1.94E+86 2.54E+06 5.99E,05

22 INCH RADIUS 7.72E.05 9.gBE+05 2.26E*95

24 INCH RADIUS 3.31E+05 4.18E+06 8.70E+04

26 INCH RADIUS 1.52E405 1.87E+85 3.52E+14

30 INCH RADIUS 3.03E.04 3.56E+04 5.29E.13

21

TABLE 17. The calculated absorbed dose (rad toLiF) at several calculatlonal surfaces and over threetime periods after discharge of fuel from reactor. Thevalues are averages over the central 2.44 m (8 ft) ofthe fuel assembly. The liner/granite gap was assumedto be VOID.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.4S YR____________ ----- ---- --_- -_._ _ ____ _ _ _

OUTSIDE ELEMENTS 8.96E+'8 1.23E+09 3.35E+98

OUTSIDE SS CANISTER 3.17E+H8 4.35E+08 1.17E+0B

OUTSIDE IRON LINER 1.85E+Z8 2.53E+08 5.61E+07

SURFACE OF-GRANITE 1.45E+03 1.99E+08 5.36E+07

WITHIN GRANITE

13 INCH RADIUS I.03E+Z8 1.4ZE+g8 3.77E+07

14 INCH RADIUS 6.39E+Z7 8.71E+07 2.32E+07

15 INCH RADIUS 4.2DE+D7 5.70E+37 1.50E+07

16 INCH RADIUS 2.71E+07 3.67E+07 9.59E+06

18 INCH RADIUS 1.12E+07 1.49E+07 3.77E+Z6

25 INCH RADIUS 4.53E+06 6.02E+06 1.49E+06

22 INCH RADIUS 1.94E+Z3 2.55E+06 6.ZaE+Z5

24 INCH RADIUS 7.77Ee05 9.95E+05 2.18E+55

26 INCH RADIUS 3.46E+05 4.43E+05 9.75E+*5

30 INCH RADIUS 5.93E+Z4 6.97Ei54 1.14E+04

22

I I

TABLE 18. The calculated absorbed dose (rad toLIF) at several calculatlonal surfaces and over threetime periods after discharge of fuel from reactor. Thevalues are averages over the central 2.44 m (8 ft) ofthe fuel assembly. The liner/granite gap was assumedto be fBled with WATER.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

OUTSIDE ELEMENTS 8.92E+08 1.23E+09 3.36E+08

OUTSIDE SS CANISTER 3.16E+08 4.34E+08 1.17E+O8


SURFACE OF GRANITE 9.87E+O7 1.35E+081 3.60E+07

WITHIN GRANITE

13 INCH RADIUS 5.71E+O7 7.65E+.7 1.94E+07

14 INCH RADIUS 3.96E+07 5.43E+O7 1.48E+07

15 INCH RADIUS 2.56E+07 3.47E+07 9.18E+96

16 INCH RADIUS 1.60E+07 2.15E+07 5.56E+06

18 INCH RADIUS 6.96E+06 9.30E+06 2.34E+O6

20 INCH RADIUS 2.69E+06 3.54E+J6 8.47E+05

22 INCH RADIUS 1.04E+06 1.34E+06 3.01E+05

24 INCH RADIUS 4.30E+O5 5.43E+O5 1.14E+O5

26 INCH RADIUS 2.02E+06 2.48E+05 4.53E+04

31 INCH RADIUS 3.26E+94 3.72E+04 4.58E+03

23

TABLE 19. The calculated absorbed dose (rad toLiF) at several calculational surfaces and over threetime periods after discharge of fuel from reactor. Thevalues are averages over the central 2.44 m (8 ft) ofthe fuel assembly. The liner/granite gap was assumedto be rfled with COMPACTED BENTONITE.

OUTSIDE ELEMENTS

OUTSIDE SS CANISTER

OUTSIDE IRON LINER

SURFACE OF GRANITE

WITHIN GRANITE

13 INCH RADIUS

14 INCH RADIUS

15 INCH RADIUS

16 INCH RADIUS

18 INCH RADIUS

2Z INCH RADIUS

22 INCH RADIUS

24 INCH RADIUS

26 INCH RADIUS

30 INCH RADIUS

2.45-5.45 YR

8.98E+08

3.20E'58

1.97E+08

6.46E'57

4. IZE+07

2.S3E+37

I1.62E+07-

I .05E'57

4.06E+ZS

1 .68E+06

7.65E.05

3.06E355

1 .68E055

2.S0E+04

RAD S

2.45-7.45 YR

1.23E 4.9

4. 39E*08

2.7#E.58

8.85E+07

5.57E+37

3.43E.57

2. 18E.57

I .41E.57

5.38E+06

2.20E.06

9.89E055

3.88E055

2.z9E+55

2. 92E+84

5.45-7.45 YR

3.37E+ZS

1.18E+08

7.27E.57

2.35E+17

1.47E+37

8.95E*26

5.651455

3.57E+06

1.32E+35

5. ISE+05

2.24E+55

S. 13Ee54

4.ZSE+84

4.14E 403

24

I

TABLE 20. The calculated absorbed dose (rad toLUF) at several calculatlonal surfaces and over threetime periods after discharge of fuel from reactor. Thevalues are averages over the central 2.44 m (8 ft) ofthe fuel assembly. The liner/granite gap was assumedto be filled with SAND/BENTONITE.

RADS

2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

OUTSIDE ELEMENTS 9.92E.08 1.23E.09 3.35E+J8

OUTSIDE SS CANISTER 3.18E+18 4.36Ee08 1.18E+98

OUTSIDE IRON LINER 1.97Ee08 2.69E.08 7.26E+07

SURFACE OF GRANITE 6.2#E+07 8.47E+07 2.27E+07

WITHIN GRANITE

13 INCH RADIUS 3.93Ee07 5.35E+97 1.42E+57

14 INCH RADIUS 2.45E*07 3.32E+07 8.71E+06

15 INCH RADIUS 1.54E+07 2.07E+07 5.36E+06

16 INCH RADIUS 9.75E406 1.30E.07 3.29E+06

18 INCH RADIUS 4.13E+06 5.47E+06 1.33E+06

20 INCH RADIUS 1.78E+06 2.32E+06 5.47E.05

22 INCH RADIUS 7.07E+95 9.13E+55 2.06E+15

24 INCH RADIUS 3.04E+95 3.83E.05 7.94E.04

26 INCH RADIUS 1.40E+85 1.72E+e5 3.22E.04

30 INCH RADIUS 2.78E+04 3.27E+04 4.82E+03

25

X io- 7.45 yr4 7.45 yr

0 15'

oL Gap material: comripacted bentonite Gap material: sand/bentonite

2.45 yr 2.45 yr

Snw

LI101

1g03

10 15 20 25 30 10 15 20 25 30Radius (in.)

FIG. S. The absorbed dose rate (rad/h to granite) outside the iron liner as a function of radius from the centerline of the fuel assembly. The values plotted are averages over the central 2.44 m (8 ft) of the fuel assembly. Thegap between the liner and the granite was assumed to be VOID, or filled with WATER or COMPACTED BEN-TONITE or a SAND/BENTONITE mixture, as shown in the legends of the plots. The parameter is time elapsedsince discharge of fuel from reactor.

26

XE 7.45 yr " X 7.45 yrX

a 'J I F'1l.p

I 105 'Gap material: Compacted bentonite Gap material: sand/bentonite

.45 yr 2.45 yr

2A5 yr 5 43.45 yr1 3

4A5 yr ~~~~~~~4.45 yr102 5.45 yr ~~~~~~~5.45 yr

lo0 .1 6.45 yr

I 00 7.45 yr745y

10-110 15 20 25 30 10 15 20 25 30

Radius (in.)

FIG. 6. The absorbed dose rate (rad/h to LIF) outside the iron liner as a function of radius from the center lineof the fuel assembly. The values plotted are averages over the central 2.44 m (8 ft) of the fuel assembly. The gapbetween the liner and the granite was assumed to be VOID, or filled with WATER or COMPACTED BEN-TONITE or a SAND/BENTONITE mixture, as shown In the legends of the plots. The parameter Is time elapsedsince discharge of fuel from reactor.

27

10o9

108 ~~~~~~~~~~~108

107 ~~~~~~~2.45-5.45 y'j10a7 2.45-5.4 5 yr

10o6

io8 ~~~~~~~~~~~~~5.45-745 yr1 o5

5.45-7.45 yr-,,

S10 5to

_ _ __1_ _4_ _ _ _ _ _ _ _ _ .2

o 0 _ _ _ _ _ _ __

V Gap material: compacted bentonite 'a 'Gap material: sand/bentonite2.45-7.45 yr 2.45-7.45 yr

w108L l

107 2.45-5.45 yr 172.45-5.45 yr

106 106

5.45-7.45 yr 5.45-7.45 yr

1 05 1 a4

103 o10 1 5 20 25 30 10 10 1 5 20 25 30

Radius (in.)

FIG. 7. The absorbed dose (rad to granite) outside the iron liner as a function of radius from the center tine ofthe fuel assembly. The values plotted are averages over the central 2.44 in (8 ft) of the fuel assembly. The gap be-tween the liner and the granite was nassunred to be VOID, or filled with WATER or COM0PACIED BEN-TONITE or a SAN D/BENTONITE mixture, as shown in the legends of the plots. The parameter Is time periodafter discharge of fuel from reactor.

28

I

lop 10Gap material: void I Gap material: water

2.45-7.45 yr 2.45-7.45 yr

107 2.45-5.45 yr

107t 752.45-5.45 yr

1(6~~~~~~~~~~~0

106 1 6.45-7.45 yr

5.45-7.45 yr

C

. 1 . 10& lot . - @ 1,Gap material: compacted bentonite l Gap material: sand/bentonite

&i 108 5-2.45-7.45 yr _ 2.45-7.45 yr

2.45-5.45 yr 107 .45-5.45 yr

5.45-7.45 5r s.45-7.45 yr105 loll~~~~~~~~0

104 -i0 4

1031 | 1 1 to3 -*10 16 20 25 30 10 15 20 25 30

Radius (in.)

FIG. & The absorbed dose (rad to LIF) outside the Iron liner as a function of radius from the center line of thefuel assembly. The values plotted are averages over the central 2.44 m (8 ft) of the fuel assembly. The gap betweenthe liner and the granite was assumed to be VOID, or filled with WATER or COMPACTED BENTONITE or aSAND/DENTONITE mixture, as shown In the legends of the plots. The parameter Is time period after dischargeof fuel from reactor.

29

our calculation. The pair 9OSr-90Y, which is essen-tially a pure beta emitter (i.e., it produces almost nogamma rays), accounts for an additional 10%, ap-proximately. If the ratio of the contribution to thegamma ray dose to the contribution to the decayheat is the same for the remaining nuclides as forthose considered, then the neglect of the remainingnuclides might produce a result 10% lower than theactual case.

The axial distribution of source strength wasentered into the calculation as a histogram, as notedabove. The 137Cs scans from which this approxima-tion was made actually show variations of about±5% along the central section of the full assembly,where the source strength was approximated as con-stant for our calculations. Since we averaged overthe entire central 2.44 m, this approximation shouldnot cause a significant error. The use of (discrete)histograms at the ends of the assembly instead ofthe (continuous) cosine curves predicted by reactortheory should likewise not produce significant errorin the results for central section.

Another source of error was neglect of thespacer grids, nozzles, and support cage. The grossgamma scans in the HEDL report4 showeddecreases of about 10% at the spacer grids. The137Cs scans, which were performed with an energywindow around 0.66 MeV, showed decreases abouthalf as large, probably because these gamma rayssuffered less attenuation than did the lower-energygammas included in the total-gamma scans.Because we averaged over the entire central section,the lack of attenuation due to neglecting the spacergrids will tend to cause our result to be slightlyhigher than the actual case. This effect is probablyless than 1%. Neglect of the nozzles at top and bot-tom should not have a significant effect on the cen-tral section. Neglect of the support cage will tend tomake our result higher than actual by less than 10%.This figure was estimated by smearing the supportcage over the entire external surface of the assemblyand calculating attenuation of a 0.6-MeV gammaray in the resulting thickness of stainless steel.

The simplification of the shield plug geometryin the model should not produce significant effectsin the central section of the granite.

No doubt there are deviations in axial align-ment between the steel liners and the holes in thegranite. The effect of this will be to increase the doseto the granite in the areas where the fuel assembly iscloser to the wall of the hole than in the ideal

geometry modeled and vice versa. If the liner weretilted with respect to the hole, such that a 50 mmchange in spacing between the assembly and thegranite wall occurred, the gamma dose at the sur-face of the granite could vary as much as 10-15%from the dose calculated with the ideal geometry ofthe model.

Uncertainty in position of the grout could alsoinfluence the results. For example, if extra groutwere placed in the liner-granite gap, part of the cen-tral section of the granite would be shielded by it.

Variation in properties of materials could alsohave an effect on dose. The density and compositionof the granite itself varies to some degree. Presenceof joints, open or filled with other minerals of dif-ferent density and composition, will affect the dose.These effects might amount to a few percent.

The MORSE-L code itself contains uncertain-ties in the cross sections, but these are generallyquite low for gamma ray interactions. In addition, asmall error arises from the fact that the gamma raysare treated by energy groups, rather than discreteenergies. Another error arises from the assumptionthat the gamma rays are totally absorbed when theirenergy falls below 150 keV. The mean free path of a150-keV gamma ray in the granite is about 27 mm,and the cross section for the granite at this energy isoverwhelmingly dominated by Compton scattering.Therefore, the gamma rays which we assume to beabsorbed at 150 keV actually would be expected totravel distances of tens of millimeters more and un-dergo several scatters before they are finally ab-sorbed. However, this effect is ameliorated by thefact that by the time a 600-keV gamma ray (approx-imately the dominant energy emitted by the fuel)has its energy reduced to below 150 keV, it has un-dergone several scatters, so that its direction oftravel is less likely to be radially outward. In addi-tion, the Klcin-Nishina cross section for Comptonscattering becomes more nearly isotropic at lowerenergies, so that lower-energy gamma rays tend tobe more nearly isotropic in their directions of travel.Consequently, although this calculation tends to es-timate the dose to be somewhat higher than actualbecause of its 150 keV cut-off, the error would notbe significant. An accurate estimate of the errorwould require comparing the results of additionalcalculations with different values of the cut-off.

A final source of uncertainty is due to thestatistical uncertainty inherent in Monte Carlocalculations. We estimate the statistical uncertainty,

30

I

i

J:Jf*averaged over tne central 2.44 m of the assembly, tobe *2% at the inner locations and +7% at points0.610 m from the centerline.

In conclusion, we estimate that the resultscalculated here are probably within 425% of the ac-

tual values. A iniore accurate estimate of uncertaintywould require more extensive calculations than ap-pear to be warranted for present purposes.

DISCUSSION

The general features of the results are as onewould expect from basic considerations and are inagreement with available experimental measure-ments. First of all, the magnitude of the absorbeddose rate at the surface of assembly D34, averagedover the central 2.44 m, is calculated to be 0.147Gy/s (5.28 X 104 rad/h) for LiF and an age of2.45 y. R. B. Davis of HEDL has reported measure-ments of exposure dose rate on assembly D04 in ahot cell on Sept. 12, 1979, prior to emplacement.4

The average of eight unshielded positions in theportion corresponding to the flat region in Fig. 2was 9.11 X 104 R/h, which is equivalent to an ab-sorbed dose rate of about 0.21 Gy/s in LiF. Ad-justing our calculation for this same age and fuelelement, we obtain .211 Gy/s (7.6 X 104 rad/h).When we consider the uncertainties mentionedabove, and the fact that the scattering environmentsare different, this excellent agreement should beregarded as fortuitous.

The decrease in dose rate with radius in the gapbetween the liner and the granite(t = 229-305 mm)is seen to be greater the higherthe density of the material assumed to be filling thisspace, as expected.

The drop-off in dose rate with radius in thegranite (r - 229-305 mm) is essentially linear onthe semilog plot, which one would expect from theexponential attenuation of gamma rays. Actually,the top curve in Fig. 6, which appears to have theleast statistical variation of all the curves, can betterbe fitted by a product of I /r and e0r terms, but theexponential term is dominant for the range in radiusof interest, so that a straight line is a good approx-imation. The "build-up" effect due to gamma rayscattering does not appear to change the shape ofthe curves, though it undoubtedly affects the slopes.

It is of interest to estimate how much of thetotal heat output of the fuel assembly is deposited inthe granite in the form of gamma rays. This can bedone by fitting the dose rate by a function of the

form Ae'/r and integrating over the volume of thegranite from the inside surface of the hole to infiniteradius. For the case of a void in the liner-granitegap, the result is about 40 W, which is less than 3%of the total heat output. It can thus be seen that thegamma-deposited heat is a small perturbation onthe total heat input to the granite surface by theconventional heat transport mechanisms.

The decrease in dose rate with time results fromdecay of the nuclides of interest. The more negativeslopes of the curves at higher ages reflect the soften-ing of the gamma ray spectrum as decay proceeds,since the higher-energy gamma rays are emitted bythe shorter-lived nuclides.

The undulations in the curves within thegranite can be attributed to statistical error in theMonte Carlo calculations.

The dose rate in granite is seen to be about 8%higher than the dose rate in LiF for the same loca-tions. This is a result of the difference in gamma rayabsorption cross sections for the elements they con-tain.

The independence of dose rate with verticallocation over most of the length of the assembly canbe explained by the large length-to-radius ratio andthe large length-to-mean-free-path ratio of the con-figuration modeled.

The variation of dose rate with time over thetime period of interest appears to be fitted well byan equation having the time dependence rn, wherethe precise value of n is different for each locationand absorbing material. For the inside surface ofthe granite hole, n is about 1.1 for all four absorbingmaterials. It appears that to match the dosescalculated here to the measured doses, and tocorrect for different emplacement times, the bestprocedure to use is as follows: first calculate n forthe location of interest by fitting calculated points,then integrate the resulting equation for dose rateover the time period used for dosimetry.

31

CONCLUSIONS

Radiation doses have been calculated forgeologic materials surrounding spent fuel emplace-ment holes in the Climax Stock quartz monzonite.The radiation dose to the granite is essentially all.due to gamma irradiation. The maximum dose oc-

curs at the inside surface of the holes. Over a five-year period, with air in the liner-granite gap, thedose is about 2.2 MGy (2.2 X lo rad). For othercases, the dose to the granite is less than this figure.

.

32

-1 I

REFERENCES

1. L. D. Ramspott, L. B. Ballou, R. C. Carlson, D. N. Montan, T. R. Butkovich, J. E. Duncan, W. C.Patrick, D. G. Wilder, W. G. Brough, and M. C. Mayr, Technical Conceptfor a Test of Geologic Storageof Spent Reactor Fuel in the Climax Granite, Nevada Test Site, Lawrence Livermore NationalLaboratory, Livermore, CA, UCRL-52796 (1979).

2. R. Carlson, R. Van Konynenburg, W. Durham, and L. Page, Planfor the Study of Radiation Effects onClimax Stock Quartz Monzonite Due to Emplaced Spent Nuclear Fuel, Lawrence Livermore NationalLaboratory internal document SFT 80-61 (April 25, 1980).

3. W. M. Quam, EG&G, Goleta, CA, private communication to Richard Carlson, Lawrence LivermoreNational Laboratory (Aug. 16, 1979 and Aug. 27, 1979).

4. R. B. Davis, Pre-Test Nondestructive Examination Data Summary Report on Turkey Point Spent FuelAssemblies DO], D04, and D06 for the Climax-Spent Fuel Test, Hanford Engineering DevelopmentLaboratory, Richland, WA (1980) TC-1693 and personal communication with Sharon Atkins of Han-ford Engineering Development Laboratory of Richland, WA (1981).

5. F. Schmittroth, G. J. Neeley, and J. C. Krogness, A Comparison of Measured and Calculated Decay Heatfor Spent Fuel Near 2.5 Years Cooling Time, Hanford Engineering Development Laboratory, Richland,WA, TC-1759 (1980).

6. Westinghouse Electric Corporation, Pittsburgh, PA, Atomic Power Division Drawing No. 541F414Rev. 3 (1969) and Nuclear Energy Systems Division Drawing No. 1144E98 Rev. 1 (1974), obtained fromJ. B. Wright, Westinghouse Electric Corporation, Advanced Energy Systems Division, Pittsburgh, PA(1979).

7. A. G. Croff, A User's Manualfor the ORIGEN2 Computer Code, Oak Ridge National Laboratory, OakRidge; TN, ORNL-TM-7175 (1979).

8. F. Schmittroth, Hanford Engineering Development Laboratory, Richland, WA, private communicationto R. Van Konynenburg, Lawrence Livermore National Laboratory (October 2, 1980).

9. C. M. Lederer and V. S. Shirley, Eds., Table of Isotopes, Seventh Edition (John Wiley and Sons, NewYork, NY 1978).

10. B. L. Cohen, "High-Level Radioactive Waste from Light-Water Reactors," Rev. Mod. Physics 49, 1(1977.

11. A. B. Smith, P. R. Fields, and J. H. Roberts, "Spontaneous Fission Neutron Spectrum of Cf2 52," Phys.Rev. 108, 411 (1957).

12. J. B. Wright, Westinghouse Electric Corporation, Pittsburgh, PA, private communication to D. A.Cantley of Hanford Engineering Development Laboratory and L. B. Ballou of Lawrence LivermoreNational Laboratory (September 14, 1979).

13. J. B. Wright, Westinghouse Electric Corporation, Pittsburgh, PA, private communication to G. J. Neelyof Westinghouse Hanford Co., Richland, WA (February 28, 1980).

14. U. S. Department of Energy, Nevada Operations Office, Las Vegas, NV, Safety Assessment Documentfor the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test Site,NV.O-210, December 1979 Draft (January, 1980).

15. Westinghouse Electric Corporation, Pittsburgh, PA, Drawing No. 6823A12, obtained from R. Carlsonof Lawrence Livermore National Laboratory, Livermore, CA (1980).

16. R. C. Weast, Ed., CRC Handbook of Chemistry and Physics, 58th Edition, CRC Press, Cleveland, OH(1977).

17. Babcock and Wilcox Co., Steam-Its Generation and Use, Revised 38th Edition, New York, NY (1975).18. E. R. Parker, Materials Data Book, McGraw-Hill, New York, NY (1967).19. T. Lyman, Ed., Metals Handbook, 8th Edition, Vol. I (American Society for Metals, Metals Park, Ohio

(1961).20. T. Baumeister, Ed., Standard Handbook for Mechanical Engineers. Seventh Edition, McGraw-Hill, New

York, NY (1967). e' I a

33

ZA1

T&MSSLIBRARY

21. Ka'mbrinslesakerhet, Handling and Final Storage of Unreprocessed Spent Fuel, Vol. II-Technical,KirnbrAnslesikerhet, Fack, S-10240 Stockholm, Sweden (1978).

22. KArnbr~nslesakerhet, Handling of Spent Nuclear Fuel and Final Storage of Vitrified High LevelReprocessing Waste, Vol. Ill-Facilities, KArnbrinslesakerhet, Fack, S-10240 Stockholm, Sweden(1978).

23. F. Maldonado, Summary of the Geology and Physical Properties of the Climax Stock, Nevada Test Site,U. S. Geological Survey, Denver, CO. Open-file report 77-356 (1977).

24. T. P. Wilcox, Shielding Study of NTS Fuel Element Shipping Cask, Lawrence Livermore NationalLaboratory, Livermore, CA, Internal Memorandum CPG-78-178 (25 Sept., 1978).

25. J. E. Faulkner, J. M. Ravets, and M. H. Lipner, Nuclear Radiation Analyses for the Storage of Un-reprocessed Nuclear Fuel, Westinghouse Electric Corp., Pittsburgh, PA, WAES-TME-2899 (Feb., 1978).

26. T. P. Wilcox, MORSE-L, A Special Version of the MORSE Program Designed to Solve Neutron, Gamma,and Coupled Neutron-Gamma Penetration Problems, Lawrence Livermore National Laboratory, Liver-more, CA, UCID-16680 (Sept., 1972).

27. T. P. Wilcox, MORSE Cross Section Library Tapes, Lawrence Livermore National Laboratory, Liver-more, CA, UCID-16683 (July, 1973).

DH/ig

34

Appendix A.Detailed results

35

. I

TABLE Al. The calculated absorbed dose rate (rad/b to GRANITE) at several calculatioual boundaries (cf.

Fig. 4) and at various elapsed times suce discharge of fuel from reactor. The liaer/grauite gap was assuwed to be

VOID.RAD PER HOUR

0%

DETECTOR NO.

12345

6789

10

1112131415

1617181920

2122232425

2627282930

3132333435

4. 50E +045.SE4+045.67E +045.90E+045.73E+04

4.67E +041.65E+042.02E+042.05E+042.05E+04

2.04E+041. 70E +049.29E +031. 17E+041.22E+04

1 .20E +041.20E +041.00E.+046.91E+039.31E+03

9.52E +039.35E +039.49E+037.64E +433.85E +02

4.62E +036.27E+036.75E+037.21E+036.49E+83

5.28E+034.67E +022.48E +423.16E+034.02E+03

3. 19E+043. 93E +044.04E+044.17E+044. 10E+04

3.30E +041. 16E+041. 43E+04I .45E+04I .44E+04

1. 44E+041.20E +046.52E+038.23E+038.56E +03

8. 39E+038.42E+037.01E E+34.85E+036.60E +03

6.69E+036.58E +036.66E+035.39E+032.66E+02

3.23E +034.39E+034.73E+035. 10E+034.56E +03

3.71E'033.24E +021. 66E +022.19E+032.79E+03

2.41 E+042.95E+043.0,7E+043. 1E +5043.13E+04

2. 50E +048.67E+031.08E+041. 10E+041 .09E+04

1.09E +049.03E+034.89E+036.21E+036.47E+03

6.31E+036.33E+035.27E+033.64E+035.0OE +03

5.03E+034.97E+035.00E+034.06E+031 .98E+02

2.42E+033.30E +033.55E+033.84E+033.44E +03

2.79E +032.43E+021.21E+021.63E+032.08E+03

1.92E+042.36E+042.46E+042.51E+042. 51 E+04

2.00E +046.85E+038.64E+438.78E+038.64E+03

8.66E+037.20E +033.87E+034.96E+035. 17E+43

5.0IE+035.03E+034. 19E+032.88E+034.00E+03

4 .00E+033.96E +033.96E+033.23E+031.56E+02

1 .91E+032.63E+032.82E+033.05E +032.74E +03

2.22E +031.95E+029.49E+011.28E+031.65E+03

1 .60E +041.96E+042.06E+042.09E +42.11 E+04

1.67E+045.66E+4037.21E+037.33E+037.18t +3

7.21 E+036.01E+033.20E +034.14E+034.31E+03

4.17E+034.18E+033.49E+032.39E+033.35E +03

3.33E+033.30E +033.28E +032.68E+031 .30E +2

1.59E+032.19E+032.34E+032.53E +032.28E+03

1.85E+031.65E+027.84E+011.06E+031.37E+03

1.38E+041.69E+041.78E+041 .80E +041..83E+04

1.44E+044.83E+036.23E +036.34E+036. 16E+03

6.21 E +035.18E+032.74E+033.58E+033.72E+03

3.59E+033.59E*033.00E+032.05E+032.89E+03

2.86E+032.85E +032.981 E+032.30E +031 .12E+02

1.36E+031.89E+032.01E+032.17E+031 .96E+03

1.59E+031.44E+026.74E+019.07E4+021 . I1E+03

1.29E+041.58E+041.67E+041.68E+041.7 1E+04

1 .34E+044.49E+035.82E+035.92E+035.75E+03

5.80E+034.84E t032.55E +033.35E+033.48E+03

3.35E+033.35E+032.80E +031 .91E+032.71E+03

2.67E +032.66E+032.62E+032. 15E+031.04E+02

1.27E+031.77E+031.87E+032.02 E+03I .83E+03

1.48E+031.35E+026.29E+019.44E+0Z1. 1OE+03

2.46 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.___- - -------- _ _ -_ _ _- - -- --- ---- -------- -------

TABLE Al. (Continmed.)

RAD PER HOUR

DETECTOR NO.____________

3637383940

4142434445

464748

w 49-J 50

5152535455

5657585960

6162635465

6667686970

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR.________ -------- -------- _ __

6.45 YR. 7.45 YR. 8.0J YR.________ _ _ _ _ _ _-

4.30E+834.23E.034.25E+033.44Ei032 * 9HE .02

1 .63E.02I .99f*032.69E.032.85Ee532.75E.03

2.88E+R32. W3E .031 .99E.021 .04E.02I1.36E403

3.01E+J32.94E+J32.96E+032.38E+031.96E+02

1 .12E+021.37E+J31.85E+031.97E+J31.89E+03

I.99E+031.58E+031.34E+026.63E+019. 30E +02

2.26E+032.20E+032.21E+031.78E+031.45E+02

8.38E+011 .02E+031.37E+031.47E+031.4JE+03

1.48E+031. 17E+039.93E+014.63E+016.83E+02

1.72E+031.87E+031.80E+031.88E+031.46E+03

1.32E+024.12E+015.61E+027.98E+027. 51 E +02

7.46E+028.08E+026.25E+026.65E+011.83E+J1

2.41E+023.42E+023.07E+023.07E+023.40E+02

1.I BE+031.27E+031.23E+031.29E+039.80E+02

9.00E+012.64E+013.71E+025.33E+024.93E+02

4.95E+025.41E+024.16E+024.39E+011. 15E+01

1.52E+022. 18E+021.99E+021.98E+022.23E+02

8.75E+029.41E+029.lJE+029.52E+J27.15E+02

6.75E+011.87E+012.66E+023.87E+023.53E+02

3.56E+023.93E+023.01E+023.17E+017.91E+00

1.06E+021.53E+021.42E+021.39E+021.59E+02

1 .80E+031.74E+031.74E+031.41E+031. 15E+02

6. 69E+017.98E+021.08E+031. 17E+031. 10E+03

1. 16E+039.23E+027.89E+013.50E+O15. 32E+02

6.90E+027.38E+027.14E+027.44E+025.56E+02

5.43E+J11.43E+012.04E+J23.00E+022.71E+02

2.73E+023.04E+ 022.33E+022.46E+J15.93E+00

8.03E+011. 16E+O21. 10E+021.05E+021.22E+02

1 .50E+J31.44E+031.44E+031. 17E+039.64E+01

5.62E+016.57E+028.94E+029.66E+029.J8E+02

9.56E+027.63E+026.62E+012.80E+014.36E+02

5.73E+026.09E+025.89E+026. 10E+024.55E+J2

4.61E+011.16E+011.65E+022.44E+022.201E+02

2.22E+0Z2.48E+02.1*91E+022.ZE+014.74E+00

6.46E+019.45E+018.99E+018.47E+019.95E+.1

1.29E+031.24E+031.23E+031.01E+1038.37E+01

4.89E+015.60E+027.66E+028.29E+027.76E+02

8. 15E+026.53E+025.77E+012.35E+013..70E+02

4.93E+025. 20E +025.04E+J25.18E+023.87E+J2

4.05E+019.82E+001.39E+022.07E+021.87E+02

1.87E+022 * I .E+021.63E+021.73E+013.98E+0J

5.44E+018.02E+017.70E+017. lIE+018.43E+01

1.21E+031. 16E+031.15E+039.43E+027.86E+01

4.60E+015.21E+027.13E+027.73E+027.22E+02

7.58E1026.08E+025.42E+812.17E+O13.43E+02

4.60E+024.85E+024.69E+024. SHE +023.59E+02

3.83E+019. 12E+J01.29E+021.92E+021.73E+02

1.73E+021.95E+021.51E+021.61E+013.67E+00

5.04E+017.45E+017. 18E+016.57E+017.82E+01

TABLE Al. (Coatued.)

RAD PER HOUR

DETECTOR NO.

7172737475

7677787980

8182838485

8687898990

9192939495

96979899

100

101102153104

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.46 YR. 7.45 YR. 8.00 YR._____ ----- -------- _- ___ ___ _______ - -__-_-------

2.99E+022.74E +516.10E+001 .03E+021.57E+02

1. 37E +021.31E+021.45E+021.40E+021.71E+01

3.82E+004.46E+015.80E+015.75E+015.95E+01

6.64E +O15.45E+017.63E+402.SSE.551.72E +01

1.94E4521. 79E+013. 51E +006.31E+019.84E+01

8.57E +51a .DIE+519.01E+018.96E+011. 12E+V1

1.70E +502.78E+013.45E+013.46E+013.45E+01

3.97E+513.41E+015.50E +008.88E-019.83E+00

1.38E+021.30E+0I2.24E+004.27E+016.78E+01

5.95E+015.45E+016.20E+016.26E+018.21E+00

8.01E-011.90E+012.28E+012.31E+512.21E+01

2.61E+012.37E+014.29E+004.11 E-016.26E+00

1.Z5E*921.03E+011.56E+003.14E+015.05E+01

4.49E+014.05E+014.64E+014.69E+016.55E+00

4. I8E-011.41E+011.65E+011.68E+011.54E+01

1.86E+011. 79E +013.54E+002.01E-014.41E+55

8.42E+518.67E+501 .G18E+002.47E+014.00E+01

3.63E +513.23E+OI3.71E+513.72E+015.55E+00

2.50E-011. 12E+011.29E+011.32E+011. 16E+01

1.43E+511.4SE+013.05E+001.06E-013.39E+00

7.07E+017.60E+099.49E-512.05E+013.32E+01

3.07E£+012.7ME+013. 11 E+013.07E+014.90E +00

1.74E-019.29E+001.06E+011.09E+019.25E+00

1. 15E+011.23E+012.71 E +506.06E-022.77E+00

6.53E+g17.17E+008.60E-011.88E.013.05E+01

2.85E +512. 50E+012.87E+012.81 E +514. 64E+00

1.50E-018.54E+009.75E+009. 9UE+008.34E+00

I.05£E+011. 14E+012.57E+004.62E-022.54E+00

2 .7OE+f12.46E +012.42E+013.41Eol12.44E+01

2.3 1E+056.48E-012.78E+005.85E+005.67E +55

4.59E+005.65E+006.51E+001. 26E +00

1. 52E +011.46E+011. 31E+012.1 IE+011.51 E+01

1. 57E+082.66E-011.54E+003.00E +002.61 E+00

2.30E +002.87E+003.21E++07.82E-01

9.68E+009.77E+007.93E+001.43E+011.0SE+01

1. 17E+001.09E-019.35E-011.73E+001.31E+00

1.27E+001.59E+002.09E+005.32E-01

6.87E+007.33E+005.32E+001.06E+018. 12E+00

9.42E-014.49E-026.25E-011. 13E+087.41 E-01

7.90E-019.52E-011.52E+003.89E-01

5.36E*+005.98E +503.93E+008.31E+506.74E+00

8.01 E-011.85E-024.54E-018.37E-014.87E-01

5.47E-016.32E-011.22E+003.02E-01

4.45E+0£5.16E+003.12E+926. 87E+005.87E+00

7.07E-017.59E-033.52E-S16.76E-013.65E-01

4.15E-014.57E-011.04E+002.45E-01

4. 11 E+554.85E +502.82E+006.35E +005.53E+00

6.69E-014.68E-033.14E-016.20E-013.26E-01

3.68E-013.95E-S19.70E-S12.23E-01

TABLE A2. The calculated absorbed dose rate (rad/h to GRANITE) at several calculatlonal boundaries (cf.FMg. 4) and at various elapsed times since discharge of fed from reactor. The liner/granite gap was assumed to befilled with WATER.

RAD PER HOUR


12345

6789

IJ

1112131415

1617181920

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.________ -------- ------- _---- --- -- ----- -_--- ---

4.59E+045.49E+045.65E+045.72E+045.76E+04

4.67E+041.58E+042.J1E+042.05E+042. 6E+J04

2.01E+048.34E+037.76E+031.22E+.4I .29E104

1.24E+041.23E+J41.02E+042.26E+J36. 17E+03

3.25E1043. 9JE+044. H02E+044.07E+044.12E+04

3. 30E +041.IIE+J41.42E+041.45E+041.46E+04

1.41E+045.79E+035.89E+038.65E+039. 12E+J3

8.81E+038.62E+J37.14E+031.52E+J34.31E*03

2.45E+042.96E+043.06E+043.09E+043.14E+04

2.5JE+048.30E+031.07E+041. 1E+041.10E+04

1.07E+044.61 E +034.63E+036.57E+036.89E+03

6.69E+036.46E+035.38E+031.18E+033.23E+03

1.95E+042.38E+042.45E.042.48E+042.53E+04

2.001E+046.58E+038.59E+038. 79E+J38.77E+03

8.5JE +034.05E+033.77E+035.28E+035.51E+03

5.37E+035. 12E+034.29E+031.02E+032.57E+03

1.62E+J41.9 9E+042.05E+J42.08E+042.13E504

1.67E+045.46E+037. 18E+37.35E+537.31E+J3

7.09E+533.75E+J33.17E+034.44E+034.6JE+J3

4. 50E +034.24E+033.58E+039.41E+J22.14E+J3

w

1.39E+J41.72E+041.77E+141;:8JE+041.84E+J4

1.44E+044.68E+J36. 2JE +536.35E+J36.29E+03

6.11EE+33.57E+032.74E+033.85E+033.97E+J3

3.9JE+033.64E1033.09E+J38.93E+021.85E+03

1.98E+031 .90E+031.93E+031.59E+035.14E+01

8.94E+021,12E+031.24E+031. 19E+031. 19E+03

1.02E+037.37E+013.83E+013.87E+528 %.3JE+02

1. 30E+041.61E+041.65E+041.69E+041.73E+04

1.34E+044.36E+035. 80E+,035.94E+035. 88E+03

2122232425

2627282930

3132333435

-t>.

* 1... .

6.69E+036.43E+J36.48E+J35.33E+032.08E+02

2.97E+0i3.84E+034.16E+034.09E+034.22E+13

3. 45E+032.43E+021.47E+J21.81.E+532.69E+03

4.7E+J034.49E+034.55E+533.73E+J31.38E+02

2.07E+032.65E1.32.91E1032.84E+032.92E+03

2.38E+031.68E+029.92E+017.17E+J21.87E+03

3.53E+033.37E+033.42E+J32.801E+039.96E401

1.55E+031.97E*032. 18E+032. 12E+J32.17E+03

1.79E+031.26E+027.23E1015.47E+021.41E+03

2.8JE+032. 67E+032.71E+032.23E+037.62E+01

1.24E+131.56E+031.73E+031.68E+031.7ME+03

1. 42E+031.01E+025. 59E1+14.61E+021. 13E+03

2.31E1432.21E+J32.25E+031.85E+136. 14E+01

1.03E4031.31E+031.44E+03

.1.39E+031 .4JE+03

1,l9E+038.46E+414.55E+014.15E+J29.53E+J2

5.71E+J33.50E+032.55E+033.61E+033.71E+J3

3.65E+J33.39E+032.89E+538.74E+021.73E+J3

1.84E+J31.77E+J31 .8J1+531.48E+534.73E+J1

8. 37E+021.04E+031. 16E+03.l I E1+J3

1.IIE+03

9.581E.26.92E+013.54E+013.76E+027.79E+J2

TABLE A2. (Continued.)

RAD PER HOUR

DETECTOR NO.

3637383940

4142434445

4647484950

5152535455

5657585960

6162636466

6667686970

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.___- - -------- -------

…- -------- __ - --------

2.63E+03 1.82E+03 1.36E+03 1.08E+03 9.01E+02 7.80E+02 7.30E+022.69E+03 1.87E+03 1.39E+03 1.10E+03 9.13E+02 7.84E+02 7.31E+022.20E+03 1.67E+03 1.32E+03 1.07E+03 9.02E+02 7.78E+02 7.26E+022.38E+03 1.65E+03 1.22E+03 9.57E+02 7.85E+02 6.66E+02 6.18E+021.64E+02 1.12E+02 8.34E+01 6.58E+01 5.46E+01 4.69E+01 4.38E+01

1.26E+02 8.44E+01 5.92E+01 4.32E+01 3.6E+01 2.53E+01 2.23E+011.29E+03 8.71E+02 6.34E+02 4.91E+02 4.00E+02 3.38E+02 3.13E+021.75E+03 1.19E+03 8.66E+02 6.70E+02 5.45E+02 4.60E+02 4.25E+021.64E+03 1.13E+03 8.42E+02 6.70E+02 F.61E+02 4.86E+02 4.56E+021.77E+03 1.22E+03 9.05E+02 7.14E+02 5.91E+02 5.08E+02 4.74E+02

1.71E+03 1.17E+03 8.63E+02 6.78E+02 5.69E+02 4.78E+02 4.46E+021.53E+03 1.05E+03 7.78E+02 6.10E+02 5.02E+02 4.28E+02 3.98E+029.96E+01 6.68E+01 '4.95E+01 3.97E+01 3.36E+01 2.96E+01 2.80E+014.41E+01 2.75E+01 1.89E+01 1.41E+01 1.12E+01 9.32E+00 8.58E+008.07E+02 5.45E+02 3.99E+02 3.12E+02 2.57E+02 2.20E+02 2.04E+02


2.42E+02 2.14E+02 1.97E+02 1.87E+92 1.80E+02 1.74E+02 1.71E+022.19E+01 1.39E+01 l.OlE+01 8.17E+00 7.08E+00 6.41E+00 6.14E+003.18E+02 2.09E+02 1.50E+02 1.16E+02 9.55E+01 8.17E+01 7.62E+014.88E+02 3.17E+02 2.27E+02 1.75E+02 1.43E+02 1.22E+02 1.14E+024.76E+02 3.16E+02 2.31E+02 1.82E+02 1.52E+02 1.32E+02 1.24E+02

4.94E+02 3.24E+02 2.31E+02 1.76E+02 1.42E+02 1.19E+02 1.10E+024.96E+02 3.25E+02 2.32E+02 1.77E+02 1.43E+02 1.20E+02 l.llE+024.15E+02 2.81E+02 2.06E+02 1.61E+02 1.33E+02 1.13E+02 1.05E+021.83E+02 8.25E+01 4.00E+01 2.16E+01 1.35E+01 9.71E+00 8.53E+001.51E+01 1.08E+01 8.51E+00 7.23E+00 6.44E+00 5.90E+00 5.67E+00


TABLE A2. (Continued)

RAD PER HOUR

DETECTOR NO. 2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.________ -------- -------- _- _ _ _ _ _ - - ----- __--__ _ __

7172737475

2. 16E*021 .49E+013. I9E.00f6.59E+017. 12E+81

1 .44E.029. 36E .001. 78E+084.H3E.01I3.98E.01

1 .83E+526.55E400f1 .1OE.0ff2.73E.012.52E.01

76. 77787980

8182838485

8687888995

9192939495

96979899

100

lol102103104

8.46E.017.37E 0019.7ffE+818.73E.015.64E.00

2.59E8002.*44E.013.*46E.014.08E.013.28E.01

3. 64E.013. 4HEH I03.85E8005.42E-011.1IIE.01

1 .68E.012.2 1E.011 .36E.011 .94E.011 .75E.01

3.45E.084. 3NE-022.*71 E*N304.15E800S. SHE+00

2.36E*092.49E8003.72E.E9a.95E-01

5.*06E+J14.47E+015.97E+015.56E+013.50E+00

1.42E+001.42E+011.84E+012.34E+011.85E+01

2.02E+012.04E+012.65E+002.23E-J16.J3E+J0

8.37E+0J1.20E+017.32E+001.J6E+011.05E+01

2.55E+JO2.62E-02I .43E+Jff1.79E+002.36E+00

1.21E+0J1.23E+001.91E.005.92E-01

3.39E+013.01E+014.03E+813.90E+012.44E+00

8.37E-019.25E+001.llE+011.55E+011. 17E+01

1.27E+011.36E+012.05E+009.20E-023.58E+00

4.65E+JJ7.35E+004.42E+0E6.32E+007.05E+00

2.J6E+0J1.91E-028. 17E-018.09E-011.18E+00

6.87E-016.44E-J11.1ME+004.63E-01

7.84E.015 03E+887.53E-HI2.83E+81I.79E+H1

2.55E.012.24E+012.93E+012.97E+011. 86E+00

5.29E-816.67E8007.60E+001 * 14E+018.21E800

8.*85E+001 .N1E.011 .71E5003.78E-022.*31 E+ .00

2.96E8005 .02E8003.82E+004. 1 1E+H5S. 22E+00

1.77E+001. .6E-#25.B1E-014. JOE -ff6.54E-01

4.39E-013.*62E-017. 19E-814 .05E-H1

6.27E+014.13E+005.62E-011.61E+011.41E+01

1.99E+011.79E+012.27E+012.41E+011.52E+00

3..54E-015.23E+005.81E+009.19E+006.33E+00

6.66E+0J8.01E+0J1.51E+001.56E-021.61E+J0

2.15E+003.78E*032. 30E .002. 9JE .004.18E.00

1.58E+001.45E-023.28E-012.28E-014.13E-J1

3.13E-012.18E-015.30E-013.76E-J1

5.20E+813.55E+004.46E-011.35E+011. 18E+J1

1.68E+.011 .51E+011.85E+012.05E+01I .30E+0J

2.46E-014.35E+004.82E+007. 84E+005.21E+00

5.34E+006.74E+J01.38E+006.44E-031.18E.00

1.72E+003.06E+001.89E+002. 18EJ0+3.54E+00

1.45E+001.37E-022.25E-011.55E-012.94E-01

2..44E-011.39E-J14.27E-013.60E-01

4.77E+013.32E+004.03E-J11.25E+01I. 1E+01

1.56E+011.40E+011.68E+011.90E+011.21E 00

2.05E-014.01E+004.46E+007.33E+004.79E+00

4.84E+006.24E+001.32E+503.97E-031.02E+0O

1.58E+002.79E+001.75E*001.91E+J03.29E+H0

1..39E+001.34E-J21.87E-011.34E-012.55E-01

2.2JE-011. 12E-013.91E-013.53E-01

*-r

TABLE A3. The calculated absorbed dose rate (rad/b to GRANITE) at several calculatiomil boundaries (cf.

Fig. 4) and at various elapsed times since discharge of fuel from reactor. The liner/granite gap was assumed to befuled with COMPACTED BENTONITE.

RAD PER HOUR

DETECTOR NO.

12345

678910

1112131415

1617181920

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR._- -- - -- -- - -- -- - -- -- - -- -- - -- -- - --------__ _ _ _ _ _ ____ __ _ _ _ _ _ _ _ _ _ _ _ _

4.55E+045.49E+045.61E+045.90E+045.82E+04

4.64E+041.60E +042.03E+042.06E+042. 11E+04

2.05E+041.71E+049.69E +031.24E+04I .30E +04

1.29E+041.27E+04I .05E+043. 14E+034.14E+03

3.23E9043.91E+043.99E+044.19E+044.14E+04

3.29E+041. 12E+041.43E+041.46E+041.49E+04

1.44E+041.20E+046.77E +038.7 1E+039.19E+03

9. 12E+038.92E+037.32E +032.19E+032.91E +03

2.45E+042.97E+043.04E+043.18E+043.14E+04

2.49E+048.42E+031 .08E+04I, 10E+041 . 12E+04

1.09E +049. 10E+035.06E+036.58E+036.95E+03

6.87E+036.70E+035.49E+031.64E+032.20E+03

1.95E +042.38E+042.43E +042.55E +042.52E+04

1.99E+046.69E+038.65E +038.82E+038.92E+03

8.64E+037.26E+034.00E+035.25E+035.54E+03

5.46E+035.32E+034.35E+031.30E+031I76E+03

4P

1.63E+041.99E+042.04E+042.14E+042.10E +04

1.66E+045.55E+037.22E+037.36E +037.41E+03

7.19E+036.06E+033.30E +034.39E+034.62E+03

4.54E+034.41 E +033.61E+031.08E+031.47E+03

1.44E+031.45E+031.45E+031 . 16E+034.81 E+01

6. 70E +028.72E+029.26E+029.27E+029.22E+02

7.53E+024.05E+011. 69E+014.03E+025. 10 E+02

1. 42E+041.72E+041. 76E+041.85E+041.82E+04

1.44E+044.77E +036.23E +036.36E+036.37E+03

6.19E+035.23E +032.82E+033.80E +033.98E +03

3.90E+033.79E+033.10E+039. 27E+021 .28E +3

1.31E+041.61E+041. 64E+041.74E+041.70E+04

1. 34E +044.45E+035.82E+035.94E+035.94E+03

5.782E+034.89E+032.63E+033.56E +033.72E+03

3.64E+033.53E+032. 90E +038.65E +021. 20E +03

2122232425

2627282930

3132333435

4.30E +034.28E+034.27E+033.45E +031.1 IE+02

2.09E +032.66E+032.75E+032.75E+032.75E+03

2.29E+031.21E+026.91E+011.29E+031.58E+03

2.98E+032.97E+032.96E+032. 38E+037.95E+01

1.43E+031.82E+031.90E+03I .90E +031.90E+03

1.57E+038. 17E+014. 39E+018.78E +021.07E+03

2.22E+032.22E+032.21E+031.77E+036.32E+01

1.05E+031.35E+031.41E+031.42E+031.41E+03

1.16E+036.07E+013.01E+016.41E+027.87E+02

1. 75E +031 .75E+031.75E+031.40E+035.39E+01

8. 202E+021.06E+031 .12E+031.12E+031 .11 E+03

9.12E+024.83E+012.19E+014. 97E +026.17E+02

1. 23E+031.24E+031.25E+039.93E+024.42E +01

5.67E +027.45E+027.95E+027.95E+027.91E+02

6.452 +023.53E+011.35E+013. 40E +024.38E+02

1. 15E+031. 16E +031. 17E+039.26E+024.26E+01

5.25E +026.93E+027.42E+027.42E+027.37E+02

6.01 E +023.31 E+011.22E+013.14E+024.09E+02

a .

..1 I .

TABLE A. (Conted.)

MAD PER HOUR

A.w~

DETECTOR NO.

3637383940

4142434445

464748495J

5152535455

5657585960

6162636465

6667686970

1.68E+031 .BNE 5031.78E+031. 48E+037.80E+J1

3.66E+J1B. 2WE+021.J2E+J31.B5E+031. I9E+N3

1.17E+039.86E+025.82E+013.73E+015.14E+02

7.06E+026.85E+J27.56E+027.67E+026.29E+02

3.35E+012.65E+012.43E*022.96E+022.82E+J2

2.85E+023.01E+023.22E+021.74E+J15.55E+0N

9.73E+J11.22E+021.21 E.21.20E+021.35E+02

1. 14E+531.23E+031.22E+03I.JJE+035. 19E+J1

2.33E+015.38E+026.87E+027.03E+028.066+J2

7.87E+026.64E.023.83E+012.16E+013.40E+82

4.66E+024.58E+025.05E+J25. 13E+024. 19E1+2

2.23E+J11.75E+011.56Ei02I. 9OE +021.82E+J2

1.82E+021.97E+022.17E+J21. 15E+013.43E+50

5.75E+017.42E+017.41E+017.45E+018.66E+01

8.35E+029.03E+029.J9E+027.38E+023.83E+J1

1.64E+J03.84E+025.02E+025.11 E+025. 926+052

S.73E+024.83E+J22.76E+011.43E+012.45E+02

3.35'E+023.34E+023.66E.023.71E+023.03E+02

1.64E+JI1.26E+011. I1E+021.33E+021.29E+02

1.27E+021.41E+021.61E+028.31E+J02.43E+0J

3.78E+014.97E+015.02E+015.14E+516.10E'+JI

6.52E+J27.07E+027.17E+025.79E+023.J6E+JI

1.25E+JI2.94E+023.92E+023.98E+024.63E+J2

4.43E+J23.74E+022.13E*811.06E+.011 .9JE+02

2.57E+022.61E1022.83E+022.87E+822.34E+02

1.31E+.19.59E+008.47E+011.01E+029.95E+01

9.60E+011.08E+J21.29E+026.S1E+0#1.92E+J0

2.75E+013.63E+013.70E+013.86E+014.65E+01

5.36E+025.82E+025.94E+024.77E+022.58E+01

1.02E+012.38E+023.23E+023.27E+023.81E+02

3.61E+023.05E+021.75E+108.61E+J01.56E+J2

2.09E+022. 15E+022. W3E+022.33E.02I .90E+02

1.l1E+017. 6E +006.92E+018.14E+018.14E+01

7.71E+018.80E+011.09E+025. 40E +001.64E+00

2.16E+012.85E+J02.92E+013.10E+013.76Et01

4.57E+J24.97E+J25. 10E+024.58E+022.27E+11

8.66E+002.J0E+022.76E+022.79E+023.25E+12

3.05E+122.58E+021.49E+017.42E+.01.33E+02

1.76E+021.85E+021.94E+021.96E+021.61E+02

9.72E+JJ6.24E+105.91E+016. 85.E+06.95E+.1

6.48E+J07.44E+019.55E+014.66E+001. 47E+00

1.79E+512.35E+012.42E+012.61E+013..19E+01

4.25E+J24.62E1+24. 761E+23. 80E+022.14E+01

8.J06E+J01.85E+022.57E+022.60E+023.03E+12

2.82E+522.39E+021. 38E+016.97E+001.24E+J2

1.63E+021.72E+121.80E+021.82E+J21.49E+02

9.18E+J05.69E+.005.50E+016.33E+016.47E+J1

5.99E+016. 90E+019.01E+514.37E+001. 40E+50

1.65E+012.16E+012.22E+112.42E+102.96E+01

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.______a _ -_ _ - _ ---- _- --- --- -- __----- -_ - --___

TABLE A3. (Coutinued.)

RAD PER HOUR

DETECTOR NO.

7172737475

7677787980

8182838485

8687888990

9192939495

96979899

140

101102103104

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.__---- - -------- -------- --- --- _ _ __ __ ____ ___--- - --------

1.20E +021.05E+013.06E+004.26E+015.G Z8E+01

5.46E+015.36E+016.97E+014.57E+014.40E +00

1.01E+001.75E+012 .50E+012.32E+012.30E +01

2.85E+012.31E+013.10E+002.90E-018.02E+00

1.22E+011. 14E+011.03E+012.15E+011.23E+01

1.71E+004.40E-059.91E-012.40E +002.96E+00

2.48E+001.76E+003.10E+008.01E-01

7.56E+016.74E+001.58E+002.51E+0l2.99E+01

3.20E+013.20E+014.41 E +012.72E+012. 5 8E +00

4.32E-019.23E +001.37E+011.30E+011.33E+01

1.70E+011.32E+011.62E+00l . 19E-014.20E +00

6.03E+006.38E+005.67E+001.33E+017.40E +00

9.34E-012.18E-055.05E-01I.01E+001.45E+00

1.22E+008.93E-011.53E+005.84E-01

5.28E+014.75E+009.41E-011.64E+011.87E+01

2.10E+012.12E+013.04E+011.84E+011.67E+00

1.90E-015.42E+008.38E+008.12E+008.68E+00

1.11 E+018.66E+009.40E-014.90E-022.41E+00

3.30E+004.04E+003.49E+008.74E+004.99E +00

S .68E-011.25E-052.98E-014.36E-017.83E-01

6.46E-014.8BE-018.40E-014.89E-01

4.02E+013.59E+006.51E-011 . I8E+0I1.29E+01

1.53E+011.54E+012.24E +011.39E+011 .18E+00

8.74E-023.56E+005.73E+005.66E+006.31E+00

7.92E+006.39E+006.00E-012.01E-021.52E+00

2.05E+002.86E+002.38E+006.03E+003.72E+00

3.83E-018.63E-062.06E-011.92E-014.70E-01

3.72E-012.89E-015.26E-014.44E-01

3.28E+012.87E+005.13E-019. 15E+009.69E +00

1.21E+011 .2E+011.75E+011.I15E+019.00E-01

4.41E-022.58E+004.30E +004.32E+005.00E+00

6.01E+005.19E+004.19E-018.29E-031.05E+00

1.44E+002.23E+001.78E+004.32E+002.99E+00

2.82E-016.99E-061.65E-018.88E-023.14E-01

2.33E-011.85E-013.76E-014.20E-01

2.80E+012.39E+004.42E-017.53E+007.74E+00

1.02E+011.00E+011.43E+01I .08E+017.22E-01

2.55E-022.03E+043.46E+003.53E+004.20E +00

4.81E+004.49E+003.15E-013.42E-437.80E -01

I .13E+001.85E+00I.42E+003. 18E+002.54E+00

2.22E-016.08E-061.45E-014.34E-022.30E-01

1.56E-011.26E-012.97E-014.05E-01

2.62E1012.20ME004.17E-016.90E+007.00E+00

9.45E+009.19E+001.30E+019.45E+006.53E-01

2.03E-021.83E+003.15E +003.23E+003. 90E +00

4.34E+004.22E+002.76E-012.12E-036.80E-01

1.021E001.71E+001.29E+002.73E+002.36E+00

1.99E-015.84E-061.38E-013.02E-022.01 E-01

1.28E-011.05E-012.69E-013. 99E-01

1

TABLE A4. The calculated absorbed dose rte (rtd/h to GRANITE) at several calculational boundaries (cf.

Fig. 4) and at various elapsed tis since discharge of fuel from reactor. The liter/granite gap was assumed to be

fild withbSAND/BENTONITL

RAD PER HOUR


12345

6789

10

1112131415

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.________ -------- -------- ------ - _-------- -------

4.76E+H45.44E+045.68E+J45.75E+045.77E+04

4. 8HE+041.61E,+042.03E+042.08E+042.01E+04

2.05E+041.74E+049.87E+031.28E+041.29E+04

3.37E+043.86E+044.04E+044.J9E+044. 1 E+804

3. 40E+041. 13E+041.44E+841.47E+041.42E+14

1.45E+141.23E*046.91E+039.01E+039.09E+03

2.54E+042.93E+043.07E+J43.12E+043.13E+04

2.57E+048.5JE+031.09E+041. 12E+J41 .07E+04

1 .09E+049.24E+035. 18E+036. 80E+036.88E+03

2.01E+042.35E+042.46E*042.51E 042.51E+04

2.04E+046.75E+038.69E+J38.91E+038.54E+03

8.73E+037.35E+434.09E+035.42E+035.5JE+03

1.67E4041.97E+042.XSE+042.11E+542.1IE*54

1. 70E+045.68E+537.26E+037.44E+037.12E+J3

7.27E+936. 1 1 E+033.39E+034.52E+J34.59E+03

1617181920

2122232425

2627282930

3132333435

1.24E+J41.28E+841.03E+043.13E+034.01E+03

4.07E+J34.00E+534.21E+033.57E+H31.24E1+2

2.00E+032.56E+032.74E1032.56E+032.6JE+J3

2.21E+031.43E+028.79E+J11.3JE+J31.59E+J3

8.72E1.38.99E+037.19E+032.17E+532.81E+03

2.83E+032.79E*032.92E*032.47E+138.22E+01

1.36E+J31.77E+031.89E+031.76E+031.80E+3

1.52E+J39.92E+J15.83E+018.78E+021.09E+03

6.57E*536.76E+035.42E+031.62E.032.11E+03

2.12E+032. 10E+J32.18E1031.84E+J35.84E.51

1.00E+031.32E+031. 45E.031.31E+J31.34E+J3

1.13E+537.46E+J14. 16E+016.38.E+028 .07E+82

5. 24E+035.37E.034.31E+031.27E+J31.68E+03

1.68E1J31.68E+031.72E*031.45E+834. 40E+01

7.78Et021.J4E+031.15+E531.04E+031.86E+.3

8. 88E+025.98E+813.16E+014.91E+J26.36E+02

4.36E+134.46E+033.59E+031.05E,031 4E1+53

1.40E+031 .4E1+031.42E+03.* 19E+53

3.49E+J1

6.36E142'8.63E+029.INE+528.64E+028.84E+02

7.32E+125.J4E+012.53E+013. 97E1025. 27E+02

1 .43E+041. *70E+041.77E+041,83E+041. 83E+04

1.46E+044.81E+036.27E+J36.41E,36.13E+03

6.26E+035.25E+032.9JE+J033.89E+033.97E+03

3 76E+033.83E+J33.09E+.38.93E+021.21E+53

1.20E+131.22E+031.22E+031.52E1032.87E+J1

5.39E+J27.41E+127.78E+J27,44E1'27.61E1+2

6.25E+0241.'E+512. 10E+J13 .33E+J24.52E+J2

1.33E+041.59E+041.65E+541.72E+041.71E+04

1. 37E+144.49E+035.86E1035.99E+035.73E+03

5.85E+034. *90E+032.70E+033.63E+033.71E+03

3.51E+033.58E+132.89E1.38.30E+021.13E1+3

1. 12E+031. 14E+031.13E+J39.44E+J22.62E+01

5.01E+026.91E+027.24E+526.95E1427. 11E+02

5*81E+024.14E1+11.93E+013.57E+024.22E+02

TABLE A4. (Conied.)

RAD PER HOUR

0%


3637383940

4142434445

4647484950

5152535455

5657585960

6162636465

6667686970

1.69E+031.65E+031.67E+031.34E+031. 13E+02

6.03E+018.12E+021.03E+031.06E+031 .03E+03

1 .08E+038.45E+029.33E+014.31E+015.39E+02

6.79E+026.95E+026.61E+026.85E+025.65E+02

5.85E+011 .92E+012.25E+023.42E+022.93E+02

2.83E+022.75E+022.50E +022.32E+011 .12E +401

1. 15E+021.37E+021.25E+021.29E+021.36E+02

1. 15E +031. 12E+031. 14E+039.14E+027.73E+01

3.93E+015.41E+026.92E+027. 18E+026.89E.02

7.27E+025.68E+026.50E+012.78E+013.54E+02

4.43E+024.64E4.24.36E+024.56E+023. 79E+02

4. 11EE+011.20E+011.44E+022.23E+021.88E+02

1.77E+021.79E+021.66E+021.50E+016.96E+00

7. lOE+818.59E+017.75E+017.98E+018.76E+.01

8.49E+028.30E+028.40E+026.75E+025.66E+01

2.76E+013.90E +025.06E.025.27E+025.01E+02

5.33E+024.16E+024.78E+011.94E9012.53E+02

3.16E+023.37E+023.14E+023.30E +022.77E+02

3. 12E+018.23E +001.01E+021.59E+021.32E+02

1.22E+021.27E+021.22E+021 .06E+014.62E+00

4.79E+015.91E+015.30E+015.44E+016.19E+01

6.67E+026.55E+026.58E +026.33E+024.38E+01

2.06E+012.99E+023.94E+024.13E+023.92E+02

4.17E+023.27E+023.68E+011.46E+011.95E+02

2.43E+022.62E+022.43E+022.55E+022.17E'02

2.5 1E+016. 10E+007.67E+011.22E+029.99E+01

9.17E+019.67E+01*9.78E+018.01E+003.24E+00

3.48E+014.40E+013.92E+014.04E+014.71E+01

5. SZE +025.43E+025.43E+024.42E+023.56E+01

1.62E+012.42E+023.24E+023.41E+023.24E+02

3.43E+022.70E +022.95E+g11. 16E+011.58E+02

1.97E+022. 15E+021.98E+022.08E+021 .80E +02

2. 12E+014.82E+006. 19E+019.95E+018.02E+01

7.36E+017.81E+018.32E+016.42E+002.38E+00

2. 70E +4013.49E+013.09E+013.20E+013.81E+01

4.71E+024.68E+024.64E+023.8IE+022.99E+01

1.33E+012.04E+022.76E+022.92E+022.79E+02

2.93E+022.33E4022.44E+019.59E+001.34E+02

1.67E+021.83E+021.69E+021.76E+021.55E+02

1.85E+013.99E+005.22E+018.45E+016.72E+01

6. 18E+016.57E+017.37E+015.37E+001 .81E+00

2.19E+012.90E+012.56E+012.66E+.013.21E+01

4.39E+024.37E+024.32E1+023.56E+022.75E+O1

1.21E+011.88E+022.57E+022.72E+022.61E+02

2.72E+022.17E+022.23E+01B. 80E +001.24E+02

1.55E+021.70E +021.57E+021.63E+521.45E+02

1.74E+O13.66E+004.83E+017.85E+016. 20E +041

5.72E4016.07E+0,16.98E+014.95E+001 .58E+00

1.99E+012.66E+012.35E+012.45E+012.97E+01

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.…_______ -------- -------- -------- -------- _______ _-_____

TABLE A4. (Cpontinued.)

RAD PER HOUR

-Jh

DETECTOR NO.

7172737475

7677787980

8182830485

8687888990

9192939495

96979899

10

1011J2103104

1 .01E028.61E+J06.63E O04.95E+015.53E+01

5.09E*015.55E+016. 18E4014.20E+013. 70E +00

3. 19E+002.25E+013.16E+012.36E+.S2.22E+01

2.31E+011.91E+J12.57E60S3.06E+887.02E+.0

1.36E+011.28E+018.63E+J01.38E+B18.41E+00

1. 48E+.01.87E-J11.59E+802.94E*004.86E+N0

2.21E.501.72E+.01.30E+.07.92E-J1

6.4#E 015.24E+£J03.84E .002.92E+.13.27E+f.1

3.03E+012.99E+013.92Ei012.64E*011.93E+06

1.66E+001.22E+811.79E+011.34E.0i1.22E+01

1.35Ei011.16E.SI1.16E*081.93E£-0O3.36E+00

7.29E+006.86E.SS4.87E+088.08E*8f5.43E+08

7.28E-J11.23E-017.25E-011.39E4SS1.98E+S0

9.12E-011.02E£005.87E-01,5. *80E-01

4.56E*813.64E+502.4HE 001.94E+812. 15E+oS

2.BIE+811.97E+812.71E+011.89E+011. I5E+ff0

9.40E-017.27E+801. 12E.S18.52E+.S7.69E.0S

8 *8E+tOS8.0 £0E+ 0J5.75E-011.28E*001.78E+08

4.39E+904.15E£02.13E+0S5.i8E+J04.85E+80

4.12E-018.31E-023.64E-J17.21E-011.56E+00

3.78E-016.83E-J12.8JE-014.87E-J1

3.57E+f12.83E+001. 65E +B1.40E+811.56E+S1

1.47E+.11.44E+012.J2E+011.50E+o17.91E-01

5.78E-014.78E.007.66E+0S5. 99E+065.51£E+.0

6.33E.0S6. 1 1E+0J3.25E-018.71E-S11.57E+NS

2.96E+802.83E.081.28E+003.59E+803.36 E£.

2.76E-S15.75E-J22.11E-014.21E-016.31E-01

1.58E-015.03E-011.43E-014.43E-01

2.99E+l12.38E+N5I.,12E+081. 1NE+81I..22E+81

1. 16E+011. 14E+011.59E+011.28E+016.ISE-J1

3.83E-013.27E+J05.70E8004..60E+004.39E+S0

4.93E*805.85E+B0J2.217E-016.05E-017.45E-01

2.21E.002.14EJ009.06E-J12.66Et0J2.9£E*00

2. 17E-SI4.04E-J21.45E-012,.;0E-J14.25E-11

2. 69E-J24.ONE-018.02E-J24.2JE-J1t . 6 9 -5

2.62E+£12, 1 1 E+.08,1lE-0i9t.54E*SSI.51E+01

9.73E+H#9,53E+001.30E+811. 14E015.26E-O1

2.68E-S12.41E+.034.55E +03,76E+003.75E+0S

4.56E+.S4.39E+001.67E-0I4,24E-S15,81E-S1

1. 77E+001.75E*H07.27E-012.06ES0S2.76E+0.

1.88E-J12.85E-J21. 15E-J12.09E-J13.17E-S1

2..9JE-023.36E-014.92E-024.J5E-J1

2.48E+012. E.3006.91E-018.29E+0J9.29E+o0

8.99E'fi08.82E.00.* 19E+H1

1.08E.+014.94E-0i

2.26E-012.9 E+004.#SE +003.44E+0S3.52E+J0

3.73E+004.13E£001.52E-013.51E-015.27E-S1

1. 61£E +H1.61E+S06.70E-011.84E+£82.66EtJ0

1. 79E-S12.36E-021.06E-S11.86E-012.80HE-J1I

1.88E-023.11E-Si3.91E-023.98E-01

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.J0 YR.________ -------- -------- -- - _ _ --- - ___ ___---__ -

TABLE AS. The calculated abcorbed doce rate (rad/b to LiF) at several calculatioaal boudaries (ef. Fig. 4)

awd at various elapsed ties since dischae of fud [rom reactor. The ler/gr1aite gap wa assumed to be VOID.

RAD PER HOUR

.o.o@0

DETECTOR NO.

12346

6789

10

1112131415

1617181925

2122232425

2627282930

3132333435

4.17E*045.09E6045.25E6+46.46E+045.31E+04

4.33E6041.52E+04I .06E+041.89E+041.90E +04

1.89E+041 .57E+048.57E+031.58E+041. 12E+04

1. 10E+04I 156E +49.22E.036.36E+038.566E+3

8.76E+038. WE +038.73E+037.03E+033.54E+02

4.24E+035.76E+036.256E036.62E+035.96E603

4.85E+034.286E+22.28E+022.89E+033.69E+03

2.95E+043.61E*043.74E+043.87E+043.806E+04

3.06E+041.07E+041.32E+041.34E+041.33E+04

1.33E+041. 11E+046.014E037.59E*037.89E+03

7.74E+037.76E+036.46E+034.46E+036.06E+03

6. 15E,036.05E+036.13E+634.56E+032.44E+02

2.96E.034.53E+034.34E6034.68E9+034. 19E+03

3.40E+032.97E+0Z1.53E +022.OE 8032.56E+03

2.23E+042.74E+042.86E+042.92E+542.90E +04

2.32E+048.01E+039.98E+031.01E+041.00E+04

1 .HOE+048.34E+034.5BE+035.72E+035.96E+03

5.016E+035.84E+034.86E+033.34E+034.65E +03

4.63E+034.57E+034.65E+033.73E6031.81E+02

2.22E6.33.03E+033.26E+033.52E+633.16E+03

2.566E+032.23E+021.14E+021.49E +31.91E+03

1 .78E+042.18E*042.28E+042.33E.042.33E+04

1. 865E+046.33E+037.97E+038.1 IE+037.97E +03

7.99E+036.65E+033. 6E+6034.57E+034.76E+03

4.62E+034.64E+033.86E+032.66E+033.68E+03

3.6 66+033.64E+033.64E+032.97E+031. 436E02

I .76E6032.41E5032. S6E+032. S#E+032.SIE+03

2.04E+031 .79E+028. 71 E 011. 18E+031.51E+03

1.49E+041.82E6041 .91E+041 .94E+041.96E+04

1.S55E+045.23E+036.66E+036.77E6036.62E*03

6.66E+03. 55E+03

2.95E.033.82E+033.97E+03

3.84E+033.856E.033.21E+032.20E +033.086E03

3.066+033.04E+033.02E+032.47E+031.196+02

1.46E+032.#16E*32. 156E032.3ZE +032.09E+03

1.69E+031.51E+027.19E+019.72E+021.26E +03

1.28E 941.S7E+041.65E+041.67E+041.569E+04

1.33E+044.46E+03S.756E+035.85E+035_69E+03

5.73E+034.79E+032.53E+B33.30E+033.43E+03

3.30#E633.31E+032.77E+031.88E +32.66E6+3

2.63E+032.62E+032.686+032.12E+031.52E+52

1.25E+031.74E+031.84E+031.99E+B31.80E+B3

1.46E+031.31E+026. 18E+018.31E+921.08E+43

1. 19E+041.46E+041.546+041.566E+04I .59E+04

1.25E+044. 15E+035.37E+B35.47E+035.31E+03

5. 356E034.47E+032.36E+033.08.E+033.21E+03

3.086E+033.096E+032. 58E6+B31.76E+032.49E+03

2.46E+032.456E+032.41E+.31.98E*039.567E+01

1.16E+531.63E+031.72E+031.BSE+031.68E+03

1.36E+031.24E+025. 78E +Ml7.74E+021.01E+03

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.50 YR.____ __ ________-_ -------- ----- --_ _ . __

.. * ~~I

TABLE A5. (Contined.)

RAD PER HOUR

DETECTOR NO. 2.45 YR. 3.45 YR. .4.45 YR. b.45 YR. 6.45 YR. 7.45 YR. 8. 0YR.________ -------- -__ _ _ - -----_ _- _ __ _ _ _ _ _ _

36373839'40

4142434445

4647484950

5152535455

5657585960

6162636465

6667686970

3.95E+033.89E+033. 90E +033.16E+032.65E.02

1.49E*021.83E+J32.46E+J32.61E+J32.52E+53

2.64E+ .32.1I E+J31.83E+029.51E+J11. 25E +J3

1.58E+031.71E+J31.65E+J31.72E+J31.34E+J3

1.21E+J23.77E+J15.14E+027.30E+J26.89E+£2

6.84E+027.4JE+O25.73E+J26. 12E+J11.68E+JI

2.21E+J23.14E+J22.82E£022.82E+823.12E+Z2

2.76E+532. 7E +032.71E+J32. 18E+J31.8HE+02

1.02E+021. 26E+531 .70E+J31.81E+031.73E+03

1.83E+J31.45E+031.23E+J26.07E+J18. 52E+02

1.J8E+031. 17E+031.13E+031.18E+,38.99E+02

8.24E+012.42E+J13.4JE+024.88E+J24. 53E+02

4.53E+024.96E+J23.81 E+024.J4E+J11.05E'+J1

1.4JE+J22. NNE +021.82E+J21. 81 E+022.04E+02

2.08EJ032.J2E+J32.82E..031.63E+J3I .33E+J2

7.66E+1J9.32E+021.26E+031.35E+031.28E+J3

1.35E+531.07E+039. IJE+014.24E+J16.25E+02

8.J1E+028.62E+028.33E+J28.72E+J26.55E+J2

6.17E+J11 .71E+012.44E+J23.54E+J23.24E+02

3.26E+023. 6HE +522.76E+022.92E+017.25E+J0

9.73E+J11 .4HE+.21 .3JE+021.27E+J21.46E+02

1 .66E+031.650E+J31 .6JE+031.29E+83I .56E+02

6. 12E+J17.31E+829.91E+021.07E+03I.01E+J3

1 .06E+638.46E+027.23E+J13.Z0E+014.88E+02

6.32E+026.77E+026.54E+J26.82E+025.1JE+02

4.97E+o11.31E+011.87E+J22.74E+J222.49E+02

2.5OE5 22.79E+02'2. 14E+022.27E+J15.44E+J0

7.35E+011.07E+021.01E+029.66E+JI1.12E+J2

1.38E-+31.32E+J31.32E+031.07E4538.83E+01

5.14E+JI6.02E+J28.19E'+J28.86E+028.32E+02

8.76E+026.99E+J26.J7E+J12.57E+J13.99E .2

5.24E+J25.58E'+025.39E+025.59E+024. i7E+J2

4.22E+S1'1 .6E+Bl1.51E+022.23E*022?02E+02

2.83E*822.27E+021.75E+J21.87E+H14.36E+00

5 91E+018.65E+.1'8.27E+J17.77E+019,09E+JI

1.19E+031.14E+031. 13E+039.25E+O27.67E+01

4.47E+015,13E+027.01Et027.60E+027.11E+HZ

7.47E+f25.98E+0Z5.29E+012.15E+013.39E+J2

4.51E+024.77E+J24.61E'+024.74E+023.55E+02

3.71E+019.J0NE+0J1.28E+021.89E+021.'71E+02

1.71E+J21.931+521.49E+J21.6#E.513..66E+05

4.98E+017.34E+J17.J8E*+16.53E+J17.'70E+J1

1.1 E+J31.J6E+03I.J5E+J38.65E+.27.2J1E+O1

4.2JE+0l4.77E+026.13E+J27.J8E+J26.61E+.2

6.94E+J25.58E+024.97E+J1I.99E+JI3. 15E+02

4.21E+Z2'4.44E+.24.3JE+JZ4. 45E£+023.29E+J2

3.5JE+JI8.36E+001.18E+J21.76E+J21.59E+02

w

1.58E+J21.79E+J21. 39E+521.49E+013.38E+JJ

4.61E+416.82E+016.61E+£I6.03E+017. 14E+01

TABLE AS. (Condinuel)

RAD PER HOUR

DETECTOR NO.

7172737475

7677787980

8182838485

8687888990

9192939495

96979899

100

101102103104

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.

2.74E+022.61E+016. 1SE+009.49E +011.44E+02

1.26E+021 .20E +021.38E+021.28E+021.62E+01

3.63E+004.07E+015.33E+015.44E+015.45E+01

6.13E+015.03E+017.31 E +003.32E+001. 58E.1l

2.48E+012.28E+012.22E+013.16E+012.40E +01

2.40E +006.00E-012.56E+005.43E+005.23E+00

4.22E+005.41 E+005. 28E +001.515E+00

1.78E+021.73E+013.74E+005.81E+019.82E+01

7.88E+017.34E+019.75E4518. 21 E+011.07E+01

1.66E+002. 54E+013.17E+013.33E+013.16E+01

3.67E+013.16E+015.33 E +002. 18E+008.99E+00

1.40E+011.36E+011.20E +011. 95E+011.53E+01

1.70E4002.48E-011.42E+002.8 1Ee002.4 1E+00

2.12E+002.83E+003.06E+007.13E-01

1.26E+021.28E+012.54E+003.93E+016.21E+01

5.47E+014.99E+016. 14E+015.74E+017.96E+00

8.35E-011.74E+012.09E+012.26E+012.02E+01

2.42E+012.20E+014.21E+001 .67E +005. 72E+00

8.88GE+009.20E +007.26E+001.33E+011. 10E+01

1.32E+001.03E-018.64E-011.64E+001.22E+00

1. 1BE+001.63E+002.02E+004.84E-01

9. 57E+011.03E+01I .91E+002.89E +014.63E+01

4.14E+013.70E+014.69E+014.30E+016.42E+00

4.79E-011.29E+011.52E+011.69E+011.41E+01

1.74E+011.67E+013.SE+001.43E+004.03E+00

6.31E+006.95E+004.87E+009.87E+008.78E+00

1.0 IE+004.31E-02S.79E-011.09E+006.95E-01

7.34E-011.05E+001.50E +003.55E-01

7.71E+018.'73E+001.55E+002.28E +013.67E +01

3.35E+012.95E+013.83E+013.41E+015.50E +00

3.23E-011.02E+011. 18E+811.35E+011 .06E+Z1

1.33E+011.36E +013.06E+001.32E+003.09E +00

4.92E+005.72E+003.60E+007.81E+007.48E+00

9.70E-011.87E-024.22E-018.21E-014.60E-01

5. 12E-017.55E-011 .22E+002.76E-01

6.47E+017.71E+001.31 E +001.89E+013.04E+01

2.84E +012.47E+013.25E+012.82E+014.88E +00

2.48E-018.49E+009.77E +901. 13E+018.46E+00

1.08E+011. I SE+Ol2.73E+001.21E+002.53E +00

4.09E+004.96E+002.86E+006.47E+O06.6ZE+00

8.73E-018.56E-033.29E-016.72E-013.48E-01

3.91 E -015.86E-011.05E+002.24E-01

5.98E-017.31E+001.23E+001.74E+012.79E+01

2.64E+012. 28E+013.03E+012.58E+014.64E+00

2.25E-017.80E +008.96E+001.05E+017.63E+00

9.83E+001.07E4012.60E+001. 19E+002.31E+00

3.78E+004.67E+002.58E+005.95E+006.29E+00

8.35E-015.85E-032.94E-016.20E-013.12E-01

3.48E-015.28E-019.82E-012.04E-01

TABLE A6. The calculated absorbed dose rate (rid/h to LiF) at several calculational boundaries (cf. Fig. 4)and at various elapsed times since discharge of fuel from reactor. The liner/granite gap was assumed to be filledwith WATER.

U'


12345

6789

i0

1112131415

1617181920

2122232425

2627282930

3132333435

RAO PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.001YR.

.4.25E.04 3.01E+84 2.28E.04 1.81E.04 1.5fi1E34 1.29E'34 1.20Ee345.09E+I4 3.62E+04 2.75E*04 2.2ftE.04 1.84E*34 1.60Ee54 1.49E.345.24E.04 3.71E.54 2.84E'04 2.27E.3f4 1.90Ee34 1.64E.34 1.53Ee345.30Ee04 3.77E404 2.87E.04 2.30E+04 1.93E.54 1.67E*54 1.56E*#45.34E.54 3.82E404 2.91E.04 2.35E'04 1.97E.54 1.71E.N4 1.60E'04

4.33E.04 3.H6E.54 2.32E*04 1.85E.04 1.S5E404 1.33E'34 1.25E4041.46E'+Z4 1.82E.04 7.66E*03 6.07E403 5.04E+03 4.32E.03 4.03E.031.86E404 1.31E.34 9.92E*33 7.93E.03 6.63E153 5.73E*53 5.36E4031.90E.04 1.34E$04 1..02E.084 8.12E.33 6.78E4#3 5.86E.3f3 5.48E.f331.91E+94 1.35E+84 1.M02Ee04 8.10E+E3 6.75E.33 5.81E.03 5.42E*83

1.85Ee34 1.31Ee04 9.85E.03 7.85Ee03 6.55E*03 5.65E403 5.28E0337.70E.+03 5.34E*03 4.26E*03 3.74Ei33 3.46E.53 3.29E+03 3.23E0338.62E.+03 .6.N3E.03 4.52E.33 3.58E+03 2.96E+03 2.54E*03 2.36E.031.13E+84 7.97E.33 6.05E.03 4.86E433 4.N8Ee03 3.55E+83 3.33E8331.19E.34 8.39E.03 6.35E.03 5.07E.03 4.23E*53 3.65E403 3.41E*03

1.15E404 8.11Ee3N3 6.16E.53 4.94E.03 4.14Ee03 3.59Ee33 3.36Ei031.14E+04 7.95E.03 5.96E+83 4.72E*83 3.91E.03 3.35E+83 3.13f.039.37E.03 6.58E.03 4.96E+03 3.95E+83 3.31E 433 2.84E*53 2,.66E.034.35E.53 3.02E.33 2.25E.03 1.77E453 1.46E+83 1.24E*03 1.15E+Z35.67E+03 3.96E*03 2.97E.03 2.36E.3f3 1.97E*33 1.73fEI33 1,591.03

6.ISE.03 4.32E.33 3.24E.03 2.57E*03 2.12E453 1.82E+83 1.69E.035 9ffE.03 4.12E+03 3.09E*33 2.45E433 2.03E453 1.74E'03 1.62E+#35:96E.33 4.1BE+03 3.14E*3Y3 2.49E+.33 2.07E+03 1.77E.33 1.65E0334 9#E.33 3.43E*83 2.57E.53 2.3f4E+03 1.70E+03 1.46E.03 1.36E+03~1.91E.32 1.27E,092 9.13E+4Z1 6.99E+AY1 5.63E+01 4.71E+81 4.34E+01

2.72E+03 1.9ffE+03 1.42E.03 1.14E+N3 9.48E+02 8.19E.02 7.66E.323.53E*83 2.43E.3f3 1.81E*03 1.43E+03 I 19E*03 l.0f3E*03 9.59gE.023.82E.03 2.67E*03 2.NNE+63 1.59E+83 1.'32E+.03 1.14E.33 1.06E.033.02E.33 1.89E*03 1.25E*53 8.56E.02 6.08E.02 4.42E432 3.76E4323.88E+63 2.68E*83 1.99E.83 1.56E+03 1.28E4903 1.09E.93 l.flE.f33

3.13E.03 2.18Ee03 1.64E*03 1.31E.33 1.09E*3N3 9.39E432 8.78E.+822.23E.02 1.53E+N2 1.15E.02 ~9.28E.31 .7.74E'B1 6.74E401 6.33E.011.35E.32 9.89E.31 6.62E.01 5.12E.01 4.1.6E'U1 3.51E.01 3.25E.011I.82E'03 1.25E+'33 9.27Ee32 .7.27E432 5.98E.02 5.18E.02 4.74Eu322.47E.03 1.72E.3f3 1.29E.33 1.04E403 8.73E4N2 7.6NE40f2 7.14E.02

TABLE A6 (CAnud)

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR.________ -- -- - -- -- -____ _ __ __ _ _ __

DETECTOR NO.

3637383940

4142434445

4647.484950

5152535455

5657585960

6162636465

6667686970

6.45 YR. 7.46 YR. 8.00 YR.- -__ ___________

2.41E+032.47E+032.02E+032.18E+031.48E+02

1. 15E+021. 18E+031 .60E +031 . 51 E +031.63E+03

1.57E+031 .40E +039. 15E+O14.05E+017.40E +02

9.37E+021.O1E+031.04E+031.05E+039.06E+02

2.22E+022.01E+012.92E'+024.47E+024.36E+02

4.55E+024.55E+023.81E+021.68E+021.37E+OI

1.46E+021.82E+021 ,69E+021.71E+022.04E+02

1.67E+031.71E+031.53E+031.51E+031.02E+02

7.70E+017.97E+021.09E+031.04E+031. 12E+03

1.07E+039.64E +026.13E+012.53E+014.99E+02

6.25E+026.73E+027.01 E +027.04E+026.11 IE+02

1.95E+021.27E+01I .91E+022.91E+022.89E+02

2.99E+022.98E+022.57E+027.58E +019.78E +00

9.42E+011. 12E+021 .07E+021.09E+021.31 E+02

1.24E+031.28E+031.21E+031. 12E+037.55E+O1

5.40E4015.81E+027.92E+027.72E+028.28E+02

7.9IE+027.12E+024.55E+011.74E+013.65E+02

4.55E+024.90E +025.11 E.+025. 11 E+024.44E+02

1.81E+029.22E+001.37E+022.08E+022. 1 IE +02

2.13E+022.12E+021.89E+023.67E+017.72E+00

6.74E+017.69E+017.50E+017.56E+019.08E+01

9.90E+021.01E+039.83E+028.76E+025.97E+01

3.94E+014.50E +026.13E+026.14E+026.53E+02

6.21E+025.58E+023.64E+011.29E+012.85E+02

3.55E+023.82E+02.3.97E+023.94E+023.42E+02

1 .71E+027.43E+001.06E+021.60E+021.67E+02

1.63E+021.62E+021.48E+021 .99E+016.54E+00

5.25E+015.80E+015.71E+015.68E +016.77E+01

8.26E.028.37E+028.26E+027.18E+024.96E+01

2.97E+013.66E+024.99E+025.13E+025.41 E 02

5. 12E+024.59E+023.09E+011.03E+012.35E,02

2.93E+023.13E+023.25E+023. 20E +022.77E +02

1.64E+026.44E+008.72E+011.31 E+021.39E+02

1.32E+021 .30E +021.21E+021.24E+015.82E+00

4.36E+014.70E +014.64E +014.52E +015.35E+O1

7.16E+027.18E+027.12E+026. 10E+024.27E+O1

2.31E+013..09E+024.21E+024.45E+024.65E+02

4.38E+023.92E+022.72E+018.58E+002.01E+02

2.51E+022.67E+022.76E+022.69E+022.33E+02

1.59E+025.82E+007.46E+O11. 12E+021. 20E +02

1.I IE+021 .O9E+021.04E+028. 92E+O05.32E+00

3.78E+014.01E+013.94E+013.77E +014.41E+01

6.69E.026.70E+026.66E+025.66E+023. 98E+01

2.04E+012.86E+023.89E +024..17E+024.34E+02

4.08E+023.64E+022.57E +O17. 91 E +001.87E+02

2.34E+022.4SE+022.57E+022.49E+022. 15E+02

1.56E+025.5SE+006.95E+011.04E+021. 13E+02

1.03E+021.01E+029.65E+017.84E+005. 12E+00

3.54E+013.74E+013.66E+013.47E+014.03E+O1

-i


RAD PER HOUR

%A

DETECTOR NO.

7172737475

7677787980

8182838485

8687888990

9192939495

96979899109

15115210314

1 .97E+021.37E .513.* 9E .556 .54E.516.*53E+Zl

7.76E.5l6.76E+818.87E'518 .00E*915.+16E.9ff

2.*36E .002.24E.513.17E+813.68E.913.8#E.51

3.25E.913.13E+813.55E#Nff5.NIE-811 .02E*Sl

1. 55Eu912 .A3E+811.25Ee911 .78E.511.61ZE*01

3. ISE +594.18I E-522.49Ee95f3.83E+004. * ZE .99f

2.23E8902.29E.593 .A2E.95gS. 29E-01

1. 31EE028.58E*081. 71 E 9003.68E+Nl3.64E+S1

4.64E*M14 .f9E.915.45E+015.09E+813.25E*00

1.29E+J01.30E*B11.69E+012.15E+011.69E+81

1.85E+011.87E+012.44E+002.08E-015.55E+.9

7.68E+Bf1.10E+016.71E+009.72E+099.66E 05

2.33E+002.64E-J21. 31 E +091.65E.001.81E*00

1 1 17Ef+o1.12E+001.75E*005.50E-J1

9.38E+016.01E+001.05E+0J2. SHE+ .12.303E+01

3.1HEE912.76E+013.67E+813.57E+012.22E+00

7. 61 E-0-18. 47E5001.1E+011.42E+811.87E+01

1.17E+011.25E+011.89E+008.68E-J23.29E+00

4.26E+006.72E+004.04E+0J5.79E+096.48E+00

1.89E+051.98E-027.47E-J17.46E-018.31E-J1

6.B5E-J15.90E-011.01E+004.30E-J1

7.14E.514.61EC007 .08E-011.85E 011.63E+01

2.29E+012.04E+H12.67E+H12.72E+011.69E+9f

4.81E-016. 10E+006.93E+S#1.95E.917. 5HE +00

8. 1 IE .999.22E .51.58E+003.69E-022.12E+00

2.7* E+7f094.58E+2.76E+J03.77E+C04. * E0+N#

1.62E+901.69E-024.58E-013.67E-J14.22E-01

4.56E-J13.31E-916.57E-J13.76E-J1

5.71E+013.79E+005.23E-01.1.47E+.11.28E.01

1.82E+811.63E+812.07E+012.21E+Bl1.38E+00

3.22E-014.78E+005.29E8058.42E 095.78E+80

6. 11E+*07.34E.091.39E+801.64E-021.47ECJ9

1.96E.093.45E+N.52. ISE.0U2.65E+J03.84E+89

1.45E+JJ1.55E-023.JJE-J12.J9E-012.53E-J1

3.40E-012.0JE-J14.85E-013.5JE-J1

4.74E+013.26E+004.13E-J11.23E+811 .58E401

1.54E+J11 38E+ff1.68E+011.87E+011. 18E.05

2.24E-J13.97E+054.38E+H07.19E.004.75E+90

4.89EH0J6. 17E+J01.27E+so7. 90E -931 .J8E+OJ

1.57E.992.79E.051.73E*801.99E*553.24E*09

1.33E+C91.47E-J22.06E-J11.4ZE-511.81E-01

2.75E-511.28E-013.91E-Ji3.34E-J1

4.35E+013.N5E.053.71E-011.14E+811.00E+91

1.42E+011.28E+011.53E+B11.74E+611.1MEE50

1.87E-013.66E*094.5rE+806.72E+084.37E+05

4.43E+J05.72E+881.22C.995.61E-J39.39E-J1

1.44EJ052.54E+NfI.59E.191.74E.953.0IE*N#

1.2BE+fh1.44E-J21.71E-811 .23E-J11:.6JE-J1

2.52E-J1l.J2E-Jl3.5BE-J13.28E-J1

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.________ -------- -------- -------- -------- ___ ___-__ _ -_

TABLE A7. The calculated absorbed dose rate (rad/b to LiF) at severa calculational boundaries (cf. Ftg. 4)and at various elapsed times s!ce dscage of fuel from reactor. The liner/ganite gap was assumed to be filledwith COMPACTED BENTONITB.

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.55 YR.……___ …__ _- -_- -_- -_ -- --- _

DETECTOR NO.

2345

6789

10

1112131415

1617181920

2122232425

2627282930

3132333435

4.22E+045.09E+045.20E+045.47E +045.39E+04

4.30E+041.48E+041.87E+041.90E+041.95E+04

1.89E+041. 58E+048.93E+031. 14E+041 .20E +04

1 . 19E+04I .17E+149.64E+032.88E+033.79E+03

3.95E+033.93E+033.92E+033.17E+031.01E+02

1.92E+032.43E+032.52E+032.52E +032.53E+03

2.10E +031. 1IE+026.31E+01l . 19E+031.45E+03

2.99E+043.62E+043.70E+043.88E+043.83E+04

3.0SE+041.03E+041.32E+041 .34E+041.37E+04

1.33E +041. 11E+046.24E+038.03E+038.46E +03

8.40E+038.21E+036.74E+032.01E+032.66E+03

2.74E+032.73E+032.72E+032.19E+037.24E+01

1.31E+031.67E+031.74E+031.75E+031.74E+03

1.44E+037.47E+014.00E+018.05E+029.80E +02

2.27E+042.75E+042.82E+442.95E+042. 91 E+04

2.31E+047.77E+031.00E+041.02E+041 .04E+04

1.00E+048.40E+034.66E +036.06E+036. 40E +03

6.33E+036.17E+035.05E+53I.50E4+032.01E+03

2.04E+032.03E+032.03E+031.63E+035.74E+01

9.66E+021.23E+031.29E+031.30E +031.29E+03

1.06E+035.54E+012.74E+015.88E+027.20E+02

1.81E+042.20E+042.26E+042. 3 7E +042.33E+04

I.85E+046.17E+037.99E+038.14E+038.24E.03

7.98E+036.71E+033.6SE*034.84E+035.14E+93

5.03E+034.901E03A.01E+031. 19E+031.61E+03

1.61E+031 .61E+03I .61 E+031.28E+034.89E+01

7.52E +029.69E+021.02E+031 .03E+031.02E+03

8.36E+024.41E+012.00E+014.55E+025.65E+02

1.51E+041.84E+041.89E+541.981 .+41.956E04

1.54E+045. 13E+036.67E+036. 8E +036.84E+03

6.64E+035.61E+033.04E+034.04E+034.25E +03

4. 18E+034.071E+033.33E+039.88E+021.35E+03

1.32E+031.33E+031.33E+031.06E+034.36E+01

6.14E+027.98E+028.48E+028.0E +5028.45E+02

6. 90E +023.71E+01i .54E+013.70E+024.67E+02

1.32E+041.59E+441.63E1041.72E+041.68E+04

1.33E1+44.41E.036.75E+035..87E+035.881E+03

5.72E+034.83E+032. 60E +033.501E+033.67E+03

3.59E+033.49E+032.86E+038.49E+021.17E+03

1. 13E+031. 14E+031.1 SE+039.11E+024.50E+01

5.19E+026.82E+027.29E+027.29E+027.24E+02

5.91E1023.23E+011.23E+013.12E+024.01E+02

1.21£+041.49E+041.52E+541.61E1041.56E+04

1.25E+044. 11E+035.38E+035.49E+035.48E+03

5. 34E+034. 1 5E1+32.42E+033.27E+033.42E+03

3.351E+033 25E+032.67E4037.93E1+21. 10E+03

1.05E+031.06E+031.07E+038.49E1023.851E01

4.81E+026.34E+026. *80E+02

6.79E+026.75E+02

5.51E+023.03E+011. 111E012. 88E+023.74E+02

I I

I.I

TABLE A7. (Continud.)

RAD PER HOUR


3637383940

4142434445

4647484950

5152535455

5657585960

6162636465

6667686970

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.…____.__ -------- -------- _ -_ -------- -------- -------

1.54E.031 .6SE 031.63Et031.35E+J37.13E.01

3.35E+017.53E +029.39E+029 .66E t021.09E+03

1.J7E+J39.J4E+025.33E+013.39E+014.72E+02

6.47E+026.28E+J26.93E+027.03E+025.76E+02

3.J7E+012.37E+01

2.71E+022.59E+02

2.62E+022.76E+022.95E+021.6JE+015.07E+00

8,92E+011.12E+021. II E.02l.IE+021.24E+J2

I .J4E+031.12E+031. 12E+039. 2JE+024.75E+J1

2.13E+814.94E+026.29E+026. 45E+J27.38E+J2

7.21E+S26.09E+J23.51E+101.97E+J13.11E+02

4.27E+J24.20E+024.63E+J24.70E+023.83EJ02

2.04E+gI1.6JE+JI1.43E+021.73E+821.67E+J2

1 .66E+021.81E+J21.99E+021.05E+J13. 13E+00

5.27E+016.8JE+8.16.84E+016.94E+017.97E+01

7.65E+028.27E+028.32E+026.77E+J23. 50E +01

1.50E+oI3.52E+J24.59E .024.69E+025.42E+J2

5.24E.024.43E+022.53E+011.31E+012.24E+02

3.07E+023.J6E+023.35E+023.40E+822.77E+02

1.50E+011. 15E+011.01E+021.22E+021. 19E+02

1. 16EJ021.29E+021.47E+027.62E+0J2.22E+0J

3.47E+014.56E+014.65E+014.81E+J15.62E+01

5. 97E *526. 48E+H26.56E+825.31E.322.79t+81

1. 51E.012. 78E 823.59E+823.*65E+824. 24E 402

4 .06E+0f23.43E+821 .95E+819.70E8001. 74E+82

*2.36E+822.39E+822.59E+822.63E*822. 14E+82

1. 2#E+018. 7 1 E5057.74E+81.9.23 E 019. 14E+01

8.78E.019.92E.011. 18E4025.97E+B001. 75E058

2.5 1E.013.34E.013.44E+813.64E.314.28E.01

4.91E+.025.33E+J25.44E+024.38E+022.36E+J1

9.32E+002. 18E+022.95E+J22.99E+023.49E+02

3.30E+922.8SE +21.60E+J17.88E+J81.43E+02

1.91E+J21.97E+022. 10E+022.13E+021.74E+02

1.0iE+016.91E .006.32E+017.43E+017.48E+J1

7.05E+018.05E+B19.95E+014.96E+.001.49E+00

1.97E+012.62E+012.72E+012.94E+013.47E+01

4.19E+024.55E+.24.67E+823.75E+0222.07E4MI

7.93E+001.84E+022.52E+022.55E+022.98E+02

2.79E+022..37E+J21.36E+016.79E+001.22E+02

1.61E+021.69E+021.78E+021.80E+021.48E+02

8.91E+J05.68E+005.39E+016.25E+016.39E+01

5.93E+016.81E+018.74E+014.29E+001.34E+00

1.64E+012.16E+012.26E+012.49E+J12.94E+01

3.89E+024.23E+024. 35E +J23.49E+J21.96E+J1

7.38E+001. 70E+022.35E+022.38E+022.77E+02

2.SSE+022.19E+021.27E+016.38E+001. 13E+02

1.49E+021.58E+021.64E+021.66E+J21.37E+02

8.42E+005.17E+0J5.02E+016.78E+J15.95E+01

5.48E+016.32E+018.24E+014.JIE+081.28E+00

1.51E+JII.99E+012.08E+012.32E+012.72E+01

V

TABLE A7. (Coatinued.)

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.46 YR. 6.45 YR.______ - -- -- - -- -- - -- -- -__ __ _ __-_--_-_-_- __ _ _ __ _

DETECTOR NO.

7172737476

76777879as

7.46 YR. 6.00 YR.________ -------- __

1. * ZE+029.*55E 4.5

3.9 1E4.514.* 4E4.51

S.H1E 4.54.94E.516.*82E4.514.28E.514. S5E4508

6.92E *M16. ISE+001.45E+002. 30E +012.73E+01

2.94E+012.96E+514* 44E+512.50E+012.37E+00

4.83E+01A .33E+008.58E-011.50E+011.71E+01

1.93E+011.97E+013.15E+011.69E.011.53E+50

3.68E+013.27E+O05.92E-011.08E+011. 18E+51

1.41E+011.44E+012.40E+011.28E4+011.081E+00

e182838485

0'

8687888990

9192939495

96979899

10l

101102153104

9.29E-011.61E+012.29E+.12.14E+O12.14E+81

2.62E+012.12E+012.85E+002.67E-017.38E+0.0

1. 12E4+011.56E+919.65E+001.97E+011. 13E+O1

1 .57E+002.36E-039. 13E-O12.22E+002.83E+00

2.30E+O01 .70E +02.84E+0C7.40E-01

3. 98E-01D.48E+001.26E+01I.20E+011.25E+01

1.57E+011. 22E+811.49E4+00.1. I1 E-0l3.86E +00

5.53E+005.97E+O05.40E +001.22E+016.79E+00

8.54E-012.15E-034.68E-419.40E-011.43E+00

1. 13E+008.92E-011 .40E+005.39E-01

1.75E-014.98E+007.68E+007. 50E +508.25E+00

1.03E+O17.95E+008.63E-014.67E-022.22E+00

3.02E+053.80E +003.39E+007.99E +404.57E+00

5.17E-O12.03E-032.77E-OI4.07E-01a.06E-0l

6.07E-015.17E-017.68E-S14.52E-01

8.08E-023.26E+00S.24E+005. 24E+006.06E +05

7.29E+005.87E+005.51E-012.02E-021.40E+0O

1.87E+002.72E+002.37E+005.50E +003.4 £ 4+.0

3.48E-011.95E-031.94E-011.83E-015.14E-O1

3. 55E-013.32E-O14.80E-014. 1IE-01

3.00E+012.62E+004.66E-018.37E+008.85EM 0

1.1ZE+011. 13E+011.95E+S11.05E+0I8.25E-01

4. 10E-022.37E+003.93E 4.04.01 E+004.86E+00

5.54E+004.76E4+003.85E-019.31E-039.69E-Ol

1.32E+002.1.3E+001.81E+O03.95E4+002.74E+00

2.56E-0l1 .91E-031.56E-018.73E-023.69E-01

2.28E-012.36E-013.42E-013.88E-I1

2.56E+012. 18E+004.01E-OI6.88E+U07.07E+O0

9.40E+E009.39E+001.64E+019.17E+O06.62E-41

2.39E-021.86E+003.17E+O03..28E+004. 11 IE+00

4.43E+O04.12E+002.89E-014.77E-037.20E-SI

1.03E+001 .78E+001.47E+052.91E+£02.33E4+00

2.01E-011.81E-531.37E-014.52E-022.87E-01

1.56E-011.79E-012.70E -013.74E-01

2.39E +012.00E+003.79E-016.31E+£06.39E+00

8. 74E+008.64E+00I.51E+0I8.65E+005.98E-O1

1 .91E-021.68E+O02.88E+003. 01£E +003.83E+00

4.00E+003.87E+002.53E-013.66E-036.29E-01

9.30E-011.65E4+001.35E+002.50E +002.17E+99

1.81E-0-11 .79E-031.31E-013.30E-022.59E-01

1.31 E-011.59E-O12.45E-S13.68E-01

)

TABLE AS. The calculated absorbed dose rate (rad/h to LiF) at several calcutatlonal boundaries (cf. FIg. 4)and at various elapsed times since discharge of fuel from reactor. Ihe liner/granite gap was assumed to be Mledwith SAND/BENTONITE

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.01 YR.________ -------- -------- -------- -------- -------- --------

DETECTOR nO.

12345

4.41E+045.54E.+45.26E+045.33E+045.35E+54

3.12E1043.58E1043.75E+643.79E*543.81E04

2.35E5042.72E+042.85E+042.89E+042.90E+84

1.87E+042. 18E+042. 28E+542.33E+J42.33E+04

1.55E+041.82E1041 .91E+041.96E+541.95E+04

U,

67a918

1912131415

1617181920

2122232425

2627282930

3132333435

4.45E1J41.48E+541 .A8E+041.92E+041.86Ee04

1.89E+04I .61EtJ49.59E+031.17E1 941. 18E104

1. 14E+041. 18E+049.45E+032.8aE 033.68E*83

3.73E5033.67E1033.86E+033.27E*031.14E.02

1.83E1.32.35E1032.51E+J32.35E+032.38E103

2.03E+031.32E9028.05E.011.19E+031.46E+03

3. 151E+41.54E1041.33E1041.36E1841. 31 E +04

1.34E+041. 13E+146.36E+838.29E+038.37E+03

8.53E+038.28E1036.63E+131.99E1432.57E+03

2. 6E +032.56E+832.68E+132.27E.+037.54E+01

1.25E+J31.62E+J31.73E1031.62E+031.65E+03

1.40E+039.09E+JI5.33E+018.04E+129.99E+02

2.38E+047.84E+031.0E+4041.J3E+049.89E+03

1.01E+048.53E+034.77E+036.26E+036.34E+03

6.05E+036.23E+034.99E+031.48E+031.94E+03

1.94E+031.92E+031.99E+031.68E+035.36E+tI

9.15E+021.21E+031.28E+031.20E+031.23E+03

1.03E+036. 83E+J13. 80E+015.84E+127.39E+02

I.9E+4046.23E+038.02E+038.23E+037.88E+03

8.06E+036.78E+433.77E+034.99E+035.07E+03

4. 82E+034.95E+033.97E1031. 17E+031. 54E*83

1.54E+031.54E+J31.57E+031.33E+034.04E+01

7.12E+129.52E+921.01E9039.51E+029.74E+52

8.13E+125.48E+012.89E1.14.49E+025.82E+J2

1.58E+045.17E1036. 70E5+536.86E+036.57E+03

6.711E+035.64E+433.12E+034.16E+034.23E+03

4.52E+034. 11.E+533.31E+139.60E+021.28E+03

1.28E+031.29E+031. 30E903I.95E+033.21E+01

5.82E+J27.89E+128.33E+027.91E+028.59E+12

6.7JE+024.62E+012.31E+513.63E+024.82E+02

1.32E+441.58E+041.64E+041.70E+041.69E+04

1..36E+J44.44E+135.79E+535.92E+035. 66E+03

5.78E+034.85E+032.67E+033.58E+033.65E+13

3.46E+033.53E+032.85Et038. 18E+021. * 1E+03

1. 10E+1031.12E+031. I IE+139.31E+022.63E+J1

4.93E+026.77E+127.13E+026.81E+026.96E+92

5.72E+024.J3E+J11.91E+013.J4E+024.14E+J2

1.23E+141.48E+041.53E+J41.59E1841.59E+04

1.27E4544.14E+035.41E+J35.53E+J35.29E103

5. 40E+134.52E+032.48E+133.34E+033.42E+J3

3.Z3E+J33.29E+J32.66E+037.61E+J21.J3E+33

1.03E+031.J5E+531.04E+J38.65E+022.41E+11

4.57E+026.32E+026.64E+026.37E+426.50E+02

5.32E+023.79E+O51.76E+J12.81E+023. 86E+12

TABLE A&. (Coudued.)

RAD PER HOUR

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR. 6.45 YR. 7.45 YR. 8.00 YR.…_______ -------- -------- -------- -------- --------

oo


3637303940

4142434445

4647484950

5152535455

5657585960

6162636465

6667686970

I.55E+031.51E+031.53E+031.23E+031.04E+02

5.54E+017.44E+029.41E+029.75Em029.48E+02

9.85E+027.75E+028.56E+013.95E+014.94E+02

6.23E+026.37E+026.06E+026.28E+025.17E+02

5.35E+011.76E+012.07E+023.13E+022.68E+02

2.59E+022.52E+022.29E+022.13E.011.03E+01

1.06E+021.26E+021. 14E.021. 18E+021.24E+02

1.06£+031.03E+031.04E+038.38E+027.09E+01

3.61E+£14.95E+026.34E+026.59E+026.30E+02

6.66E+025.20E+025.95E+012.55E+013.24E+02

4.06E+024.25E+023.99E+024. 18E.023.47E+02

3.75E+011. 10E+011.32E+022.04E+021.72E+02

1.62E+021.64E+021. 52E+021.38E+016.35E+00

6.49E+017.86E+017.09£E017.29E+010.01E+01

7.78E+027.60E+027.69E+026. 19E+025.19E+01

2.53E+013.57E+024.63E+024.82E+02.4.59E+02

6. 1 IEfr05.99E+026.#2E+024.B8E+024 .52E.01

1. 89£E.012.74E+023.6 1E.023.76E*023.59E+02

4.88E+023.81E+024.38E+OI1.78E+012.32E+02

2.90E+023.09E+022.87E+023.02E+022.54E+02

2.85E+017.54E+009.25E+011.45E+021.21E+02

1. 12E+021. 16E+021. 12E+029.70E+004.21 E+00

4.37E+015.41E+014.84E+014.97E+015.65E+01

3.81E+022.99E+023.37E+011.34E+011.78E+02

2.22£+022.4HE +22.22E+022.33E+02I .99E+02

2.29E+015.59E+007.01E+011. 12E+029.14E+01

8.39E*018.84E+018.95E+017.34E+002.95E+00

3. IBE+014.02E+013.58E+013.68E+014.30E+01

3.14E+022.40E+022.70E+011.06E+011.45E+02

1.80E+021.96E+021.82E+021.90E+021.65E+02

1.93E+014.41E+005.66E+019.08E+017.33E+01

6.72E+017.13E+017.61E+£15.80E+002. 17E+00

2.46E +013. 19E+012.82E+012.92E +013.47E+01

5 .84E+B24. 97E*924.96E+924.#SE+023.26E.0l

1. 49E+012.*22E.022.96£.023.12E+922.97E.02

4.32E+024.28E+024.24E+023.49E+022.74 E+01

1.22E+O11.86E+022.53E+022.67E+022.55E+02

2.68E.022.13E+022.23E+O18.78E£ 051.22E+02

1.53E+021.67E+021.55E+021 .61E+021.42E+02

1.69E+013.65E+004.77E+017.71E+016. 14E+01

5.65E+016.00E+016.73E+014.92E +001.65E+00

2.00E+012.64E+O12.33E+012.43E+012.93E+01

4.02E.024.00E+023.95E+023.26E+022.53E+O1

1. 11 E+011.72E+022.35E +022.49E+022.39E+02

2.49E+021 .99E+022.04E+018.05E+001. 14E+02

1.42E+Z21.55E+021.44E+021.50E+021.32E+02

1.58E+013.35E+004.42E+017.15E+015.66E+01

5.22E+015.65E+516.38E+014.53E+001.44E+00

1.81E+012.43E+012.14E+012.23E +012.71E+01

TABLE A8. (Contimued.)

RAD PER HOUR


7172737475

2.45 YR. 3.45 YR. 4.45 YR. 5.45 YR.________ -------- -------- --------

9.28E+017 * 852.006.07E*984.SBE +015.088+01

5.86E+014.77E*003.*51 E+.02.68E*013.00E+01

4.17E+013.31E+0J2.19E+001.77E+011.97E+01

3.26E+012.57E+001.46E+0J1. 28E+011.43E+01

6.45 YR.________

2.74E+812.16E+001.02E+JJ1.OE+011. 12E+01

7.45 YR. 8.00 YR.________ --------

2.40E+011.91E+007.38E-J18. 23E+009.24E+80

2.27E+011.82E.006.28E-017.54E+008.49E+00

767778798J

U0

8 182838485

9687888990

9192939495

9697989910J

101102183I4

4.67E+014.62E+J15.65E+013.86E+JI3.39E+00

2.94E+J02.07E+012.90E+012.16E+012.03E+01

2.12E+011.75E+012.35E+002.78E+006.45E+J0

1.25E+J11. 17E+017.94E-0J1.27E+017.69E+00

1.36E+001.71E-J11.46E+882.71E+J03.74E.00

2.J4E+J01.57E+001.20E+007.32E-01

2.77E+012.73E+013.58E+012.42E+011.76f+00

1. 53E+J01. 12E+JI1.64E+011.23E+011.12E+01

1.24E+011.07E+J1I .07E.001.76E+003.08E+0J

6. 70E+006.31E+003.74E+007.45E+004.96E+00

6.67E-011.12E-016.64E-JI1.28E+001.82E+5J

8.42E-019.33E-015.4JE-015.36E-01

1.84E+i11.80E+J12.48E+011.73E+31I.0SE+00

8.66E-016.66E+001 .02E+017.80E+007.01E+00

8.07E+007.33E+JJ5.27E-011. 16E+001.63E+00

4.03E+0J3.81E+001. 952E+04.77E+003.69E+0J

3.76E-017.61E-023.33E-016.64E-019.69E-01

3.49E-016.21E-012.57E-014.E50-01

1.34E+011.31E+011.84E+011. 37E+017.19E-01

5.32E-014. 30JE+007.02E+005. 48E+205.01E+00

5.79E+005. 60E+002.97E-J17.92E-019.82E-01

2.71E+002.59E+0o1. 17E+003.30E+003.06E+00

2.51E-015.26E-J21.93E-013.87E-015.77E-01

1.46E-J14.57E-011. 31E-J14.09E-J1

1.06E+011.04E+011.45E+011. 17E+015.61E-01

3.52E-012.99E+005.22E+004.21E+003.99E+00

4.502+534.63E+J01.98E-015.5JE-016.82E-01

2.02E+801.96E+008.27E-012.44E2002.72E200

1.96E-013.69E-021.33E-012. 58E-013.87E-J1

6.17E-023.63E-017.36E-023.88E-JI

8.88E+008.69E+001. 19E+J1l.04E+014.77E-01

2.46E-J12.21E+004.12E+003.44E+J03.41E+00

3.71E+004.02E+00l.53E-013.86E-015.32E-01

I.62E+001.60+E006.62E-011.89E+002.51E+0J

1.70E-012. 6JE-021.06E-011.92E-012. 88E-01

2.67E-023.05E-014.50E-023.74E-01

8.21E+008.03E+001.08E+019.92E+004.48E-01

2.07E-011.91E+003.71E+003.14E+003.20E+00

3.41E+003.79E+001.39E-013.19E-014.82E-01

1.48E+001.47E+006.1JE-011.68E+002.42E+00

1.62E-012.16E2-29. 76E-021.71E-012.54E-01

1.73E-022.82E-J13.58E-023.68E-01

-

TABLE A9. The calculated absorbed dose (rad to GRANITE) at several calculational boundaries (cf. Fig. 4)and over three time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be VOID.

RADS

DETECTOR MO.

234S

67a9

11

1112131415

1617181921

2122232425

2627282935

3132333435

2.45-5.45 YR

7.6514589.3ZE1189.64E+189.951E+89.88E+48

7.88E+082.75E1083.41E.183.46E+83.44E+Za

3.43E+Z82.85E4881.55E+581.96E+082.54E+01

2.0BE1+82.51E+081.67E1081.15E+081.57E108

1.59E1081.57E+081.59E+181.28E+086.32E106

7.68E+071.05E5081.13E1081.21E+081.59E+48

8.83E1077.74E+063.94E+065.21E+076.64E+07

2.45-7.45 YR

1.Z4E+491.28E+091.33E+391.36E+091.35E+09

1.08E+393.75E+384.67?E084.75E4084.7ZE+08

4.70E+083.91E+182.11E+582.69E+082.8E1.8

2. 73E1082.74E1082.28E+081.57E+082.16E+18

2.18E1082.15E+382.16E1081.75E+588. 6E5+56

1.SE081.43E1481.541E+81.66E+481.49E+.8

1.21E+181.56E+Z75.33E1+67.16E+379.04E 437

5.45-7.45 YR

2.82E1483.451+183.62E+Z83.68E1+83.71E+18

2.93E+089.95Ej071.27E1+81.29E4081.26.E+8

1.27E1481.05E1485.63E+177.281+477.581E+7

.7.33E+177.35E+376.13E1074.2E1+375.88E407

5.85E+075.811+575.77E+174.711E572.28E+16

2.79E+073.86E+374.11E+074.45E+074.11E+07

3.24E+072.89E+161.38E+061.86E+072.41E+07

60

I

- ~~~~I .


RADS


3637383940

4142434445

464748495J

5152535455

5657585960

6162636465

6667686971

2.45-5.45 YR____________

7.ISE+977.00E+J77.03E+075.67E+674.68E.06

2.67E.063.26E+074.40E+074.70E+.74.58E+87

4.73E+073.75E+073.20E+061.56E+062.20E+07

2.81E4073.03E.072.93E+673.J6E+J72.32E+07

2.16E+066.24E+058.76E+061.26E+671.17E+.7

1.17E+071.29E+072.84E+J61.04E+162.69E+05

3.59E+066.14E+064.7#E.064.65E+965.26E+06

2.45-7.45 YR____________

9.54E.079.64E+879.56E+877.73E+076.38E+86

3.66E+164.41E*975.97E+576.49E+076.59E+07

6.41E+075.IIE+074.37E.062.05E.062.97E+17

3.82E+074.10E+073.96E+974.13E+873.12E+07

2.97E+068.28E .61.17E+971.69E+871.55E+67

1.56E*871.72E*071.32E+971.40E+063.53E+05

4.73E+066.81E+866.29E+J66. 14E+067.01E.06

5.45-7.45 YR____________

2.64E+972.54E*972.53E .71.06E+Z71.7JE+J6

9.8El561.16E+f71.57E+871.70E+071 .60E+07

1.68E+071.34E.071.17E4064.94E.057.67E+56

1.Z1E.071.07E.071.04E.171.07E.57S.01.+86

8.11E+052.04E+152.91E+064.32E+863.88E+J6

3.90E.064.37E+.63.37E+563.56E+058.37E+04

1.14E+561.67E+861.56E+061. 49E+061.76E+96

61


RADS

DETECTOR NO. 2.45-$.45 YR 2.45-7.45 YR 5.45-7.45 YR

7172737475

7677787980

8182838485

8687888990

9192939495

96979399

101

101152153104

4.58E+064.28E+058. 14E+041.48E+062.31E+06

2.02E+061.88E+062. 12E+062. 10E+062.68E+05

3.83E+546.5lE+0S8.05E+058.09E+058.0OE +05

9.23E +58.04E+051.33E+551.99E5042.29E+05

3.55E+053.43E+053.03E +054.93E +053.58E+05

3.76E+045.94E+033.54E+046.91E +045.93E+04

5.26E+046.52E+047.53E+041.83E+04

6.36E+065. 80E+051.02E+051.91E+063.01E+06

2.66E+062.45E+062.77E+062.76E+063.66E+05

4.29E +048.49E+05I .3E+061.04E+061.01E+06

1. ISE+Z61.06E+061.86E +052.19E+042.89E+05

4.S0E +054.49E +5Z3.73E+056.40E +5Z4.77E+05

5. 16E+046.31E+034.34E+048.41E+046.82E+04

6.24E +047.66E+049.69E +042.36E+04

1. 4SE+ZS1.53E0552. 1 HE 044.37E3557.06E+Z5

6.40E9555.70E+555. 54EZ556.SSE2559.78E Z40

4.63E+531 .90EZ552.29E+Z52.33E .552.06E .55

2.53E+ZS2.56E .555.37E Z441 .99E+536.Z1E+54

9.5ZE+541 .06E+Z57. 0E +141. 47E .551. 19EZ55

1 .41Ez443.68E452

1.50E345S. 87E.53

9.82E .531. 14E.042. 16E.045.33E+03

62

b

TABLE A10. The calculated absorbed dose (rad to GRANITE) at several calculational boundaries (cf. Fig. 4)and over three time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be filledwith WATER.

RADS


12345

67 18*910

1112131416

2.45-5.45 YR

7.74E+089.32E+089.61E+169.72E+089.84E+g0

7.S8E+J82.63E0983.39E+083.46E+083.47E+J8

3.37E+J81.43E+081.41E+082.97E+082. IE+56

2.45-7.45 YR____________

1.56E+091.28E+891.32E+591.34E+191.36E+O9

1.09E+093.59E+JVS4.65E+084.76E1084.76rE+8

4.62E+f82.09E0981.97E+182.85E+082.98E+08

1617181920

2122232425

2627282936

3132333435

2. * l1E 082.15E+1S1.70E0883.74E+971 .03E+96

1. 12E+081.07E+081 .088.086.89E+073.26E+06

4.93E+076.30E+076.23E.076.*76E.076.23E+07

5. 67E.074 .ZZE.062. 35E.061. 75E+074.46E+07

2. 90E+82.80E+ZS2.33E*085.40E+.71.49E+18

1.53E+081.46E+081.48E+J81.21E 084.34E+06

6.75E+076.58E*079.46E407-9.21E+179.39E+07

7.76E1075.49E1063. 15E+.62.48E+976.16E+07

5.45-7.45 YR____________

2.85E*183.50E4083.60E+J83.66E+.03.73E+08

2.93E+089. 591E+71.26E+861.29E+181.29E+SB

1.25E+986.61E+975.66E+.77.80.E078.0815+07

7.91E+177.46E+.76.29E+J71.66E*073.77E+.7

4.07E1.73.89Eg073.g96E+.73.25E+071 .08Ee06

1.92E072.28E1072.63E*172.44E+972.46E1*7

2.09E+071.49E+068.NHE+057.33E+161 .69E1J7

63,


RADS

DETECTOR NO.

3637383945

4142434445

4647484955

5152535455

5657585960

6162636465

6667686975

2.45-5.45 YR

4.33E+074. 44E+074.01E+073.91E+072.67E+06

1.96E+062.06E+072.81E+072.69E+072.90E+07

2.78E+072.S5E+071.60E1+066.46E+051.29E+07

1 .62E+071.74E+071.81E+071.82E+071.57E+07

5.46E+063.35E+354.95E.567.61E+067.54E+056

7.64E+067.67E+066.67E+051.87E+062.63E+05

2.45E+062.898E062.76E+062.79E+0561.60E+06

2.45-7.45 YR 5.45-7.45 YR

5.91E+076 .05E+075.59E+075.29E+073.63E1.6

2.54E+062.76E+173.76E+173.68E1+73.94E+07

3.76E+O73.38E+572.19E+068.44E+151.74E+07

2. 18E+072.34E+072.44E+072.43E+572. 11 E+07

9.61E+064.60E+5Z6.63E+061.00E +071.02E+07

I 1.E+071.02E+079.00E+062.12E+063.76E+15

3.29E+063.79E+063.65E+063.66E+062. 14E+06

1.59E+571.61E+071.58E+071.38E+579. 65E+05

5.73E+057.04E+069.59E+169. 86E1+61.04E+57

9.84E+068.83E+065.92E+051. 97E+054.52E+06

5.63E+366.02E+066.25E+566. 15E+65.32E+06

3.15E+Z61.25E+051.69E+O62.53E+062.68E+56

2.51 E+062 .51E+062.33E+062.48E+051. 13E+05

8. 43E+059.10E+059.94E +058.73E+055.47E+05

64

I

TABLE A10. (Continued.) "

RADS


7172737475

7677787980

8182938J8b

8687888990

9192939495

96979899

10

101102103104

2.45-5.45 YR

3.39E+062.21E+0S4.11E+049.46E+059.306E#5

1.19E4061.05E+061.39E4061.31E*06.*28E.04

3.22E+043.32E.054.28E+055.50E+054.30E+05

4.67E+054.78E+956.44E+044.98E+031.38E+05

1.92E50S2.79E+051.70E+052.42E+Z52.47E+Z5

6.24E+046.38E+f23.25E+J44.03E+045.34E+04

2.77E+042.76E+844.4JE+041.47E+04

2.45-7..45 YR____________

4.48E+562.94E+05S.1IE+041.23E5461.18E506

1.64E+061.37E5061.60E+061.74E+061.10E+06

3.85E+044.24E+055.31E+JS7.12E+055.42E+55

S.86E+h56.20E+059.10E+045.29E+831.67E+05

2.31E+053.46E+J52.11E+J52.94E+953.21E+J5

9.02E+848.95E+J23.84E+944.46E+J46.99E+04

3.33E+043.16E+045.35E+J42.13E+54

5.46-7.45 YR

1. ______ __

7.28E+049.97E+032.85E+J52.50E+06

3.53E+J53.16E+J54.02E+J54.2SE+J52.67E+54

6.29E+J39.26E+041.04E+051.63E+051.12E+J5

1.18E+951.42E5.52.66E+943.10E+J22.86E+J4

3.85E+046.73E+844.99E+945.17E+047.40E+504

2.78E+042.56E+025.86E+034.28E+J37.53E+5J3

5.61E+533.96E+539.48E+J36.63E+J3

65

TABLE All. The calcuated absorbed dose (rad to GRANITE) at several calculational boundaries (cf. Fig. 4)and over three time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be filledwith COMPACED BENTONITE.

RADS

DETECTOR NO.

2345

67a9

10

1112131415

1617181920

2122232425

262728293Z

3132333435

2.45-5.45 YR

7.70E5+099.33E+089.54E+081.00E5+099.87E+08

7.85E+082.67E+083.42E3083.47E+183.55E+08

3.44E Z82.87E+081.61 E +082.08E+082.19E+08

2.17E+082.12E+081.74E+085.21E+076.94E+07

7.09E+077.07E1+077.05E+075.67E107I .94E+06

3.39E+074.33E+074.5 1E+074.53E +074.52E+Z7

3.73E+071.95E+561.02E+062.08E+072.54E+07

2.45-7.45 YR

I.56E+Z91.28E+091.31E+091.38E+091.36E+09

1.08E+093.65E+084.69E+084.77E+084.85E+0S

4.70E+083.94E+082.19E+082.85E+083.00E+08

2.97E+082.90E+092.38E+087.15E+579.53E+07

9.63E+079.52E+079.61E+077.71E+072.79E+06

4.57E+075.86E+076.14E+076.16E+075.14E+07

5.05E+072.66E+061.32E+062.79E+073.44E+07

5.45-7.45 YR____________

2. 86E+083.50E+083.58E+083.76E+083.70E+08

2.93E+089.76E+071.27E+081.29E+081.30E+08

1.26E+081.57E+085.85E+077.72E+87a. 12E+87

7.98E+877.76E+076.35E+571.90E +072.59E+07

2.54E+072.55E+072.56E +Z72.54E+078.46E+05

1.18E+871.53E+071.63E +071 .63E+07I .62E+07

1.32E+077.13E+052.97E+057.18E+068.98E+06

66

I

I ~~~~~~~~Iv

TABLE All. (Continued.)

i

RADS

DETECTOR NO.

3637383940

4142434445

4647484950

5152535465

5657685960

6162636465

6667686970

2.45-5.45 YR____________

2.70E+072.91E+072.91E+172.38E.071.24E806

S.E50+051.27E+071.63E+071.67E8071.91E807

1.86E+571.57E+079.07E+655.09E+658.04E+86

1.18E+*71.09E+071.208E071.21E+8079.90E+06

S.33E+8054.13E+853.68E 064.47E+064.30E+06

4.28E8064.66E8066.16E+962.72E+058.21E+04

1.34E+061.73E+061.74E+961.75E+862.04E*06

2.45-7.45 YR____________

3.64E+073.93E8073.96E8073.22E8071.78E+06

7.30E+.51.69E+872.208E072.24E.J72.58E+807

2.5E+8072.1IE+171.21E+866.62E+J51.08E+07

1.47+8071.47E+071.69E+.71.62E+871.33E+*7

7.27E+055.46E+054.905E065. 90E8+65.74E+86

5.64E8066.21E+067.1*E+063.67E+051.11E+85

1.73E+162.24E+862.25E+862.38E+*62.71E+8*06

5.45-7.45 YR____________

9.43E8061.2E*5.71.058*078.48E+E064.55E+06

1.58E+054.19E+865.68E+065.75E+866.71E+06

6.35E+065.37E8063.07E8551.62E8052.74E8*6

3.68E+063.79E*064.04E*064.0*E+063.35E+06

1.95E+851.34E+851.22E+861.43E+061.43E+86

1.36E+*61.55E+561.91E8069.518*042.90E*04

3.82E*055.03E+8*055.16E+855.47E+056.64E+05

67

-

TABLE All. (Continued.)

RADS

DETECTOR NO. 2.45-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

7172737475

7677787985

al82839485

868788

8990

9192939495

96979899

100

151152123154

1.79E4561. 59E0553.6 9E.045. 94E0556.91 EK.05

7.48E0557.49E+0551 .03E+066.43E+0555.99E.54

9.67E 4532. 12E8553. 17E0553.S1E0553. il I E05

3.95E0553. * il E553.72E+042.66E4539.55E .04

1 .3KE+551. 49E+051 .31E.553.56E+351.74E055

2. 16EK455.59E-011. 9E*K.42.27KE343.31IE.54

2. 76E.542 .02E.543.5ZE.541 .47E.54

2.*37KE4562.59E0554.6 1E5447.46E0558.63E055

9.62E+059.52E0551 .34E+068.47E*557.58KE5-4

1 .05E.542. 58E*I53.93E0553.79E*554 .IZKE55

5 .02E.554 .03E.S54.47E+042.82E+531. 15E055

1 .64E0551 .SBEZ551. 63EZ553.92E.552.27E.55

2. 66E.546.33E-011.47E-+542. 44E .543.SSE944

3. i BE 0442.36E 0444. I SE.542.21iE.54

S.79E4555.ZSE.549. 1 SE+031.62E4551. 72E .55

2. 14E0552. 14EZ553.09E0552.03E*551.59E+54

8.43E+524.61EK.547.64EK447.68E+548.85E+54

1 .16K0559. 25K +4.57.49E453I1. 65KE4521 .88K 044

2. 65EK453.95EK453. 17EK457.62EK445.29E.54

5.11KE.531.24E-Si2.95E4531 .71E4535.66E453

4. 20EK.033.33E+036.75E+037. 4ZE 43

68

I

I

TABLE A2I Ihe calculated absorbed dose (rad to GRANITE) at ieveral calculational boundaries (cf. Fig. 4)and over three time perlods after discharge of fuel from reactor. Tle liner/granite gap was assumed to be filledwith SAND/BENTONITE.

RADS


12345

67,89.

15

1112131415

1617181920

2122232425

2627282930

3132333435

2.45-5.45 YR

8.J2E+089.22E*589.65E+J89.79E+089.82E+58

8. 1SE*582.69E+J83.43E+083.S1E+J82.39E+08

3.45E+682.92E+5J1.64E+J82.15E+082.17E508

2.08E+582.14E+081.71E+J8S. 16E+076.69E+57

6.74E+J76.66E+076.95E+J75.87E+071.93E+J6

3.23E+J74.21E+#74.49E+J74.20HE+074.228E+J7

3.62E+.72.37E5061.37E+562.07E+072.59E+J7

2.45-7.45 YR____________

l.1JE+591.27E+691.33E+091.35E+J91.3SE+J9

1.11E+093.68E+J84.79E+684.82E+584.64E+58

4.73E+584.00E+082.24E+082.94E+862.99E*+8

2.8SE+082.93E+582.3SE+087.55E+,79.16E+J7

9.25E#879.13E+579.44E+577.97E+J72. 54E+06

4.35E*,75.73E+076.99E+87s.72E+675.83E+J7

4.91E+073.26E+f61.82E'562.77E+973.52E+07

5.45-7.45 YR____________

2.93E+J83.46E+J83.61E+583.71E+J83.7JE+08

2.99E5.89.85E+J71.28E+J81.31E+081.2SE+8

1.28E+J81.07E+585.95E+J77.94E+J7

7.67E+577.95E+,76.31E*971.84E+072.46E+J7

2.46E+J72.47E+J72.SHE+072.09E+076.14E+06

1.12E+J71.S2E+J71.60E+571.52E+J71.S5E+5 7

1..29E+078.87E+564.45E+J56.99E+Jf69.26E+06

69


RADS

OETECTOR NO.

3637383945

4142434445

4647484955

5152535455

5657595965

6162636465

6667696970

2.45-5.45 YR

2.74E£+072.67E+072.71E+072.18E +071.83E+06

9.21E+051.28E+071.64E+071.71E+071.64E+07

1.73E+071.35E+071.53E +066.52E +058.36E+06

1.10E+07

1.03E+071.08E+079.55E+06

9.d4E+052.81E+053.39E+065.27E+064.43E+06

4.16E+064.21E+063.97E+063.54E+051.61 E +05

1.66E+062.02E+061.82E+061.87E+062.07E+06

2.45-7.45 YR

3.70E+073.63E+073.66E+572.95E+572.45E+Z6

1.21E+061.70E+072.21E+072.31E+072.21 E+07

2.33E+071 .83E+072.05E +062.56£E+51.12E+07

1 .39E+071. 48E+571.38E+071.44E+071.22E+07

1.36E +563.66E+054.48E+067.02E+065.84E+06

5.46E+065.59E+065.43E+064.67E+5Z2.03E+05

2.13E+062.63E+062.36E+062.44E+062.74E+06

5.45-7.45 YR

9.68E+059.56E +069.54E +067.78E+0566.25E+05

2.S6E+054.26E+065.7ZE+066.ZE +065.71E +06

6.53E+064.76E+065. 19E+052.04E+052.79E+06

3.47E+563.78E4+63.50E+063.66E +063.17E+06

3.73E+058.50E +04I.09E+061.75E+061.41E+06

1.30E+061.38E+061.47E+561.13E+054.19E+04

4.76E+056.16E+Z55.465E +055.64E +556.71E+05

70

k

: t,N

6' TABLE A12. (Continued.5 4

RADS


7172737475

76-77787980

8182838485

8687888990

9192939495

96979899

100

101102103104

2.45-5.45 YR____________

1.52E+061.25E+058.81E+046.83E+057.63E+05

7.09E+056.99E+059.19E+056.31E+054.49E+04

3.78E+042.80E+054.13E+053.12E+052.86E+05

3.15E+052.75E+052.65E+044.43E+4047.67E+04

1.69E+051.59E+059.32E+041.87E+051.32E+05

1.69E+042.81E+031.66E+043.17E+044.51E+04

2.03E+0412.40E'041.32E+041.46E+04

2.45-7.45 YR____________

2.05E+061.67E+051.08E+058.77E+059.79E+05

9.14E+059.0IE+051.20E+J68.57E+055.59E+04

4.46E+043.38E+055.14E+053.93E+053.64E+05

4.02E+053.64E+053.04E+045.49E+049.02E+04

2.08E+051.97E+051.10E+052.34Et051.84E+05

2.08E+043.52E+031.92E+043.68E+045.28E+04

2.17E+643.11E+041.47E.042.19E+04

5.45-7.45 YR________.___

5.28E+054.20E+041.98E+041.94E+052.16E+05

2.06E+052.02E+052.80E+052.25E+051.10E+04

6.84E+035.82E+041.JlE+058.15E+047.80E+04

8.72E+048.92E+043.95E+031.06E+041.35E+04

3.93E+043.81E+04I.64E+044.70E+ 045.27E+04

3.88E+037.09E+022.64E+035.08E+037.67E+03

1.32E+J37.07E+J31.48E+037.39E+03

71

TABLE A13. The calculated absorbed dose (rad to LiF) at several calculadonal boundaries (cf. FIg. 4) and overthree time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be YOiD.

RADS


12345

789

10

1112131415

1517181920

2122232425

2627282930

3132333435

2.45-5.45 YR____________

7.54E+088.52E+088.941E+89.22E+089.5S8+58

7.35E+482.54E+583.15£+083.19E+083.18E+08

3.17E*082.64E£+81.43E+081.81E+581. 88E108

1.84E.+081.85E1081.54E+581.561E.81.45E+08

1.47E+081.44E+081.46E+081 . 18E+585.81E456

7.05E+079.61E+571.03E+081.IIE+089.99E+07

8.11E+077.1ZE+553.52E+064.77E+576.59E+07

2.45-7.45 YR

9.65E+081.18E+591.23E5091.26E+591.2SE+09

1.00E+593.46E+084.32E+584.38E1084.341458

4.34E+083.61E+151.955E+82.48E+182. 584E58

2.52E+482.53E+582.11E5081.45E.581.991+08

2.55E+581.98E+081.99E+48I.61E+087.9ZE+55

9.62E+071.32E+081.41E5081.52E1581.37E+08

1.11E1089.75E5064.89E5066.47E+078.30E+07

5.45-7.45 YR

2.61E+d33.251+583.36E+583.41E+153.44£+08

2.72E1089.19E+171.171+451.19E+58I 1I145+8

1.171+459.755+075.191+076.71E+575. 99E+07

S. 75E+075. 77E5075. 55E+073.86E5075.41E+57

S.38E+075.34E+175.35E+174.33E+072.59E+56

2.51E5073.54E1+73.77E1574.58E+573.68E147

2.9SE+072.65E+561.27E+161.71E+172.21E147

72

I I.

TABLE A13. (Contdnued.)

RADS


3637383941

4142434446

4647484950

5152535455

5657585960

616263646E

666761697H

2.45-5.45 YR____________

6.58E+076.42E+976.45E+J75.20E+174.29Ee06

2.45E+062.99E.+74.93E+974.31E+074.12E+57

4.34E.073.44E+B72.94E#261.43E+062.J2E+07

2.57E+672.786E072.68E+072.BIE.172.13E.17

1.97E+165.71E+058.92E+961.15E 071.97E+97

1.07E+#71.17E1079.02E+069.57E+652.47E+68

3.29E+064.71E+164.32E+.64.27E+.64.82E+06

2.45-7.45 YR____________

9.11E+I78.76E+5J78.77E+177.19E+175.84E+CJ6

3.35E+264.f5E.175.47E+176.87E+975.58E*J7

5.84E+174.67E1+74.1IE+16I.e9E+962.72E1+.7

3.E*605 73.76E+173.63E+673.79E+972.86E+87

2.72E+167.58E+051.07E+871.55E+071.43E+07

1.43E+071.57E171.21E+071.29E+J63.24E+05

4.33E+066.24E1.65.78E+J65.64E+166.42E+96

5.45-7.45 YR

2.42E*.72.33E+872.32E+.71.89E+871.55E+16

9.14E+141.56E+M71.44E+071.66E+171.46E+J7

1.4E*971.23E+471.J7E+164.53E+857.02E+56

9.22E1+69.81E+J69.49E1.69.83E*167.34E+86

7.42E+851.87E+152.67E1.63.93E1863.57E+86

3.57E1064.H114163.EIE.163.29E+957.69E.14

1.04E+161.53E#861.46E.161.37E+061 . 61E+6

73


RADS


7172737475

7677787985

8182838485

8587888995

9192939495

96979899

1zz

151152103104

2.45-5.45 YR

4. 19E+064.15E558. 8ZE+041.36E+062.12E+56

1.86E1061.72E+062.07E+061.93E+062.58E+05

3.79E+045.95E+057.40E+057.83E+057.32E+05

S.54E+057.46E+051.29E+5S5.36E+042.09E+05

3.26E+053.21E+052.78E+Z54.58E+553.66E+05

4.12E+045.53£+033.26E1+46.49E+045.49E+04

4.85E+046.49E+047.19E+541.67E+04

2.45-7.45 YR____________

5.55E+065.69E+5S1.15E+051.76S+062.76E+S6

2.45E+062.24E+062.74E+062.53E+063.55E+05

4.38E+547.75E+8059.49E+B5I.52E+Z69.20E+85

1 .Z9E1069.85E+151.83E+057.66E+042.64E+55

4.14E+054.23E+053.42E+055.96E+054.98E+Z5

5.82E+045.90E+034.01E+047.95E+046.33E+04

5.77E+047.84E+B49.35E+042.15E+04

5.45-7.45 YR

1.36E+061.54E+052.73E+144.03E+OS6.47E+25

5.91E+055.21E+056.74E+056.ZOE+ZS9.68E+04

5.87E+B31.80E+052 .9E+052.38E+55I.88E+Z5

2.36E+552.40E+055.37E+542.31E+045.48E+04

8.72E+041.51E+056.41E+041.381E551.32E405

1.75E+043.68E+Z27.51E+031.46E+048.38E+53

9.19E+031.38E+042.15E+B44.87E+B3

74

I

TABLE A14. The calculated absorbed dose (rad to LIF) at several calculational boundaries (cf. Fig. 4) and overthree time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be filled withWATER. -

RADS


I2345

6789

10

1112131415

1617181921

2122232425

262728293J

3132333435

2.45-5.45 YR

7. 18EIE88.64E 088.91E+089.11E+.89.13E+08

7.3 LEil82.43E8083.13E.183. 21E .083.21E+08

3.11EE+1.32E+081.43E+88I. 91E+812.IZE+68

1.94E+N81.89E+88I .57E+087. 18E8079.43E+07

1.03E+989.82E+879.95t1078. 17E+072.99E106

4.52E+075.78E .76.36E+074.34Ei176.36E+J7

5.20E+073.66E+062.15E+062.98E+074.11E+07

2.45-7.45 YR____________

9.82E+681.19E+591.22E+g91.24E+891.26E8g9

1.#fE+f93.32E+.84.29E+984.39E+584.39E+98

4.26E+181.93E+981.96E+182.62E+J92.75E+98

2.67E+882.58E+982.15E+089.74E+171.29E+88

1.4E+4181.34E+881.36E+J81.lIE+183.98E+16

6.19E+877.B8E+878.68E*075.42E+878.62E+87

7.12E+175.03E+062.88E+064.03E+f.75.64E+97

5.45-7.45 YR___________

2. 64E+183.24E+183.34E08.3.39E+*13.46E+.8

2.72E+98S.85E+171. 16E+8.1. 19E+811. 19E+81

1. 1SE+186. 181E+75.21E+177. 18E+177.44E+87

7.28E+176.*8E+6 7S.8.E+172.56E+873.46E+47

3.73E8073.57E+873.63E+072. 98E+179.91E+81

1.67E+872.09E8J72.32E+071.17E+172.26E+17

1.9 18E+71.36E8067.33E+85I.15EE071.53E807

75


RADS


3637383945

4142434445

4647484955

5152S35455

5657585965

6162$35465

6667686975

2.45-5.45 YR

3.97E5074. 57E .+73.68E+573.58$+572.42E+06

1.79E+061.89E+072.57E1+72.47E+072.66E+57

2.55E+072.29E+071.47E+065.94E+0511 81E+57

1.481E.71.65E+071.66E+071.66E+871.44E*07

4.99E+063.06E+054.52E+566.88E+566.89E1+6

7.05E+567.02E+066.11E+Z61.72E +062.38E+05

2.24E1062.64E1062.53E+562.551+063.06E+56

2.45-7.45 YR 5.45-7.45 YR

5.42E1+75.54£+075.13E1+74.84E+573.29E+Z5

2.31E1+62.53E+573.45E+573.37E+573.61E+57

3.45E1+73.15E+572.Z1E+567.75E+851. WE +57

2.ZZE+072.15E+072.23E1+072.23E+571.93E+57

7.88E+564.19E+956.06E5+569. 19E+569.34E+56

9.37E+569.32E+068.24E+061. 95E+063.411E55

3.Z5E+Z63.47E+563.34E5063.35E+564.50E+06

1. 45E+071.47E+57I .45E+071.26E+078.72E+05

5. 23E+056.44E1+68.77E+569.03E1+69.52E+06

9.51E+z53.05E+065. 44E+151.821+554.131+06

5.15E+065. 511E+055.72E+565.62E+064. 88E+15

2.88E+061.14E+Z51.54E+062.31E+062. 45E1+6

2.32E+162.3ZE+562.14E+552.28E.051.02 E +05

7. 69E+Z58.30E+058. 18E1057.99E+059.43E+05

76

I

I

-. I


RADS


7172737475

7677787980

8182838485

8687888990

9192939495

96979899

100

ll102103104

2.45-5.45 YR

3.08E+062.03E+053.94E+048.64E+058.50E+05

1.09E+069.59E+051.27E+061.20E+067.57E+04

2.94E+043.04E+053.92E+055.05E+053.94E+05

4.29E+054.39E+055.93E+044.64E+031.27E+05

1.76E+052.55E+O51.SSE+052.23E+J52.27E+05

5.72E+046.47E+022.98E+043.72E+044.10E+04

2.69E+042.53E+044.03E+041.36E+J4

2.45-7.45 YR____________

4.09E+062.70E+054.87E+J41.12E+061.08E+06

1.41E+J61.25E+J61.64E+J61.59E+J6I.0IE+J5

3.51E+J43.89E+054.86E+056.54E+J54.96E+J5

5.38E+055.68E+058.38E+044.96E+031.53E+05

2.12E+053.17E+051.93E+052.70E+052.95E+05

8.27E+049.21E+023.5lE+044.11E+044.57E+04

3.30E+042.90E+044.90E+041.98E+04

5.45-7.45 YR

1.01E+J66.68E+049.30E+J32.60E+J62.28E+05

3.23E+052.89E+053.66E+053.89E+J52.44E+04

6.73E+038.46E+J49.43E+041.49E+051 .03E+05

1.J8E+051.3JE+J52.45E+043.22E+J22.62E+J4

3.61E+046.14E+J43.73E+J44.73E+J46.79E+J4

2.55E+042.74E+J25.36E+033.92E+J34.7 1E+J3

6.07E+033.62E+038.67E+J36.16E+03

77

TABLE A15. The calculated absorbed dose (rad to LiF) at several calculational boundaries (cf. Fig. 4) and over

three time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be filled with COM-PACTED BENTONITE.

RADS

DETECTOR NO.

12345

67a9

10

1112131415

1617181920

2122232425

2627282930

3132333435

2.45-5.45 YR

7.14E+088.65E+088.84E+089. 27E+089.15E+08

7.27E+082.46E+083.15E+083.21E+083.27E+08

3.17E+082.65E+091.48E+581.92E+082.02E+08

2.HZE+081.96E+081.61E+0S4.78E+076.36E+07

6.51E+076.48E +076.47E +075.2ZE+071.77E+06

3.11 E+073.96E+074.14E+074.15E+074.14E+07

3.42E+571.78E+069.34E+051.90E +072.33E507

2.45-7.45 YR

9.H9E+29I .19E+091.22E+091.28E+091.26E +59

9.98E +083.37E+084.33E+584.40E +484.48E+08

4.34E +083.64E+082.02E+082.63E +082.77E+58

2.73E +0S2.67E+082.19E+086.51E5078.73E+07

8.84E+078.82E+078.81E++77.07E.+72.53E+06

4.19E+0i5.37E+075.63E+075.65E+075.63E +07

4.63E+072.44E +561.20E +562.55E +073. ISE+Z7

5.45-7.45 YR

2.65E +083.24E+583.32E+083.49E+583.43E+08

2.71E+089.01E +071.17E+081.19E+081.20E +08

1.17E+089.84E+075.34E+077.11E"+077.48E+07

7.34E 577.15E+075.85E+071.74E+072.37E+07

2.33E+072.34E+072.35E+071.87E+077.67E+05

1.08E +071.40E +071.49E+071.49E+071.49E+07

1.21E+076.52E+052.71E+056.51E+068.ZZE+06

78

I

I5

TABLE A1S. (Continued.)1, f., -

DETECTOR NO.

3637383940

4142434445

4647484955

5152535455

5657585960

6162636465

6667686970

2.45-5.45. YR

2.47E+072.67E+072.67E +072.18E+071.13E+06

5.04E+05I .17E+571.49E+J71.53E+071.75E+07

1.70E+071.44E+078.3 1E+554.65E+057.37E+06

1.01E+079.96E+861.59E+071 .lE +079.07E+06

4.B8E+053.75E+053.37E+064.09E +063.95E+06

3.92Et+064.27E+064.75E+062.50E+057.49E+04

1.23E+061.59E+061.60E+061.64E+06I1.BSE+06

RADS

2.45-7.45 YR

3.33E+073.60E+073.62E+072.96E+071.55E+06

6.68E+051.55E.+72.01E+J72.J6E+072.37E+07

2.29E5071.93E+07I.1 IE +066.54E+059.88E+06

1.35E+071.34E+071.46E+071.49E+071.21Ee+07

6.67E+054.97E+054.48E +065.40E+065.27E+06

5.16E+065.69E+066.50E +063.37E+051.01E+05

1.58E+062.05E+062.08E+062.16E+062.49E+06

5.45-7.45 YR

8.64E+069.38E+069.56E+067.70Ee+64.16E+05

1.64E+e53.84E+065.2BE+065.27E'+066.14E+06

5.981E +064.92E+062.91E+051.40E+052.5IE+06

3.37E+063.47E+063.70E+.63.75E+563.07E+56

1.79E+051.22E+051 *iE +561.31E+561.32E+06

1.24E+061.42E+J61.75E+068.73E+042.64E.54

3.49E+054.63E+054.81E+055.19E+056.11 E+05

79


RADS

DETECTOR NO. 2.4S-5.45 YR 2.45-7.45 YR 5.45-7.45 YR

71 1.63E.36 2.16E+06 S.29Ee3572 1.45E.35 1.91E+55 4.61E.5473 3.37E.04 4.20E.14 8.33E+0374 S.35E.05 S.83E.55 1.49E+5575 6.32E*55 7.89E.55 I.S7E.35

76 6.88E+05 S.S5E455 1.98E+Z577 6.92E.05 8.92E+Z5 2.O5E05578 1.ZSE+26 1.39E.36 3.43E'5579 5.90E+05 7.76E'Z5 1.96EeZS81 5.55E.Z4 6.96E.14 1.46E+14

SI 8.91E403 9.7ZE.33 7.83E.1282 1.95E+05 2.37E.55S 4.23E+1483 2.90E,05 3.60E'55 7.AUIE.3484 2.78E.55 3.49E+85 7.13E+2485 2.94E+05 3.79Ee.05 S.S9E+04

86 3.64E'55 4.62E+05 9.79E+0487 2.86EtI5 3.70E+05 9.44E+8488 3.42E+04 4.IIEI54 6.87Ee5389 2.48E+03 2.66E.53 1.S1E45291 *8.83E+04 1.IGE+05 1.73Ee54

91 1.27E455 1.55E.J5 2.37E.5492 1.39E+85 1.77E+05 3.78E+9493 1.25E+05 1.58E+25 3.ZIE*0494 2.83E435 3.49E.15 6.96E.0495 1.60E+05 2.88E.3S 4.84E'34

96 1.97E+84 2.42E+Z4 4.55E.1397 S.55E451 8.87E+31 3.32E01198 1.39E+04 1.37Ee14 2.78E53399 2.IHE+04 2.27E+04 1.67E.13115 3.28E+14 3.94E+04 6.59E.13

181 2.S7E+34 2.98Ee34 4.1IEe13112 Z.Z5E.14 '2.47E.04 4.ZZE'13153 3.21E.04 3.82E.04 6.15E.53114 1.35E.54 2.04E+04 6.83E+53

80

I

b,

;C

TABLE A16. The calculated Rbsorbed dose (rad to LiF) at several calculational boundaries (cf. Fig. 4) and overthree time periods after discharge of fuel from reactor. The liner/granite gap was assumed to be filled withSAND/BENTONITE.

RADS


2.45-5.45 YR____________

2.45-7.45 YR____________

5.45-7.45 YR____________

12345

671915

I1112123.14i5

1617181925

2122232425

2627282935

3 132333435

7.43E+BS8.55E'088.94E+089.07E.589.1 1EE8

7.51Ee882.48E+083.17E+083.24E+083.13E+08

3.19E+082.78E+081.51E+581. 9BE+ .82.55E +8

1.91E+081.97E.081.58E+E84.74E5076.14E+57

6.1BE +576. 1lIE+076.37E+575.38E+071.77E+56

2.96E+e73.85E+874.11 E+073.85E+973.92E+87

3.31E+872.17E+061 .25E+061 .9ZE+072.38E.07

1 .91E.591 . ISE.591 .23E5991 .25E.591 .25E.59

1 .53E5993.39E.584.34E.SS4.45E.594.28Ee59

4.37E.583.69E.582 .56E+582.71IE5882. 74E.58S

2. 62E 9.52.69E.582. 16E.SB6.42E.578 .4NE 17

8.44E.578. 37E .578. 65E.577.3UTE.072.33E.56

3.98E.575.24E '.75.58E.575.24E .575.34E.57

4.49E.572.99E.561 .66E.562.54E.573. 22E .57

2.72E+963.20E+0B3.34E+083.44E+583.43E+18

2.77E+9B9. 1E+071.1SE+081.21E+g51. 15E+68

1. 1SE+969.91E+975.48E+877.31E+077.44E+07

7.96E+077.22E+075.81E+071.69E+972.26E507

2.25E+072.26E+072.29E.171.92E+975.63E+15

1.02E+571.39E+571.47E+571.39E+571 .42E+57

I . 18E+078. 12E+554.86E+956.39E+06B.47E506

81


RADS


3637383940

4142434445

4647484950

5152535455

5657585960

6162636465

666768697Z

2.45-5.45 YR____________

2.51E+072.45E+072.48E+071.99E+071.68E+06

8.46E+051.17E+071.55E+571.56E+071.50E+07

1.58E+071.24E+071.4AE+565.98E+057.66E+06

9.59E+Z61.01E+079.45E+069.88E+068.24E+06

8.99E+052.58E+053.1lE+064.82E+064.05E+06

3.81E+063.86E+063.63E+063.24E+051.47E+05

I.SlE+061.84E+061.66E+061.71E+061.89E+06

2.45-7.45 YR S.45-7.45 YR

3.39E+073.32E+073.35E+072.71E+072.25E+06

1.11E+061.56E+072.52E+Z72. 1E E+072.02E+07

2. 13E*071.67E+071. 88E+067.84E+Z51.02E+07

1.28E+071.35E+571.26E+071.32E+07I. IE+07

1. 24E+063.36E+054. 1E+966.42E+065.34E+06

4.99E+065. 1I E+064.97E+064.28E +551.85E+05

1 . 95 E +062.41E+062.16E+062.23E+062.55E+06

8.87E+068.75E+068.73E.067. 13E'065.73E055

2.62E0553.9ZE +06S.Z1E+065. 49E.065. 22E +06

5.52E.564.36E.064. 75E 405I1.87E.052. 55E.06

3. 18Ee553.45E+063. 25E 063. 35E.562.90E'06

3. 45E 057. 78E +049.98E8551. 60E'561. 29E+06

I 19E'561.26E.561 .34 E 061 .04E 4053..83E'54

4.34E0555.62E0554.98E0555. 15E055S. 12E'ZS

82

I

TABLE A16. (Continued.),

RADS

DETECTOR NO.

7172737475

7677787980

8182838485

868788

8990

9192939495

96979899

100

101102103104

2.45-5.45 YR____________

I .40E+061.13E+058.05E+046.25E+057.00E+05

6.49E4056.38E 405B.39E +055.79E +054.10E+04

3.48E+042.57E+053.79E+052.86E+e52.61E+05

2.89E +052.52E +052.43E +044.03E+047.05E+04

1.55E+051.46E+058.55E+041.72E +051.20E+05

1.55E+042.58E +031.52E+042.92E+044.15E+04

1.88E+042.19E+041.22E+041.35E+04

2.45-7.45 YR

1.88E+061.52E+059.85E+048 .062E +058.97E+05

8.37E+058.22E+051.09E.+067.85E+055.10E+04

4. l1E+043.10E+054.71E+053.60E+053.32E+05

3.69E+053.34E+052.79E+044.99E+048.28E+04

1.91E+051.81E+051.01E+8052.15E+051.68E+05

1.90E+043.23E+031.76E+043.38E+84.4.85E+04

2.00E+042.83E+J41.35E+042.03E+04

5.45-7.45 YR

4.83E+053.82E+041.80E+041.77E+051.97E+05

1.88E+051.84E+052.55E+052.06E +051 .00E+04

6.29E+035.33E +049.26E+047.46E +047.0SE+04

7.97E+048.18E+043.62E+039.68E+031.23E+04

3.60E+043.49E+8041.50E +044.31E+044.79E+04

3.52E+036.48E+022.42E+034.67E +037.00E+03

1.22E+036.42E+031.36E+036.82E+03

U.S. Government Printing Office: 1981/9-789402/4003

83

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Radiation Dose Calculations for Library Geologic Media ... · Radiation Dose Calculations for Geologic Media Around Spent Fuel-Emplacement Holes in the Climax Granite, Nevada Test