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SODIUM TECHNOLOGY PROGRESS REPORT
JULY-SEPTEMBER 1980
Hanford Engineering Development Laboratory
Compiled by J.M. Atwood
DOE R # c h l a n ~ l , W A
I DISCLAIMER I
Thli book was prepared as an acmuni of w a k rwnwrrd by an agency of the UnltRl Stare Governrnm!. Neliher !he united Stater Gowrnmen! mr any agencv thereof. m r any of the#. emolovm. makerany warranty, exorerr or ~ m o l ~ m . or a m r e any legal lbbtliry or r-nsibnlirv for the a r m . cornoleleneu, or urefulneu of any ~nformalion. ~PWR~UI . product. w pr- didored. or rwrewntr that 175 u= rrould not tnfr~nge p r ! ~ I e h l ormm righlr R e f e r e e herein to any rwclflc
Stales Government or any asencv ~hermf . The "#em and oe&nianr of suthors exor& herein do mt neceuar,lv state oi reflect !hose 01 the united S t a m Gowrnmpi or any apw thereof.
December 1980
APPLIED TECHNOLOGY
HANFORD ENGINEERING DEVELOPMENT LABORATORY Operated by Westinghouse Hanford Company
P.O. Box 1970 Richland, WA 99352 A Subsidiary of Westinghouse Electric Corporation
Prepared for the U.S. Department of Energy under Contract No. DE-AC1676FF02170
DISCLAIMER
This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.
HEDL-TME 80-32 UC-79a
SODIUM TECHNOLOGY PROGRESS REPORT
JULY - SEPTEMBER 1980
Compiled by J. M. Atwood
AB STR ACT
T h i s report presents a quarterly summary o f progress made a t Westinghouse U a n f o r d Company i n the areas of radioactivity control technology and sodium s y s t e m s technology.
iii
J
CONTENTS
A b s t r a c t
F igures
Tab1 es
MANAGEMENT SUMMARY
I. R A D I O A C T I V I T Y CONTROL TECHNOLOGY
A. RADIONUCLIDE TRAP DEVELOPMENT
B. F I S S I O N PRODUCT AND FUEL TRANSPORT BEHAVIOR AND CONTROL
C. FFTF HEAT TRANSFER SYSTEM R A D I O A C T I V I T Y SURVEILLANCE
D. R A D I A T I O N LEVELS I N F F T F HTS CELLS
E. DECONTAMINATION OF BREEDER REACTOR COMPONENTS
F. FFTF SUPPORT
11. SODIUM SYSTEMS TECHNOLOGY
A. S I L I C O N COMPOUND PARTICULATE EFFECTS
B. SODIUM FROST TECHNOLOGY
C. COLD TRAP TESTING
D. FFTF SODIUM SYSTEMS SUPPORT
E. FFTF FUEL F A I L U R E MONITORING
F. FUEL F A I L U R E MONITORING -- E B R - I 1 PROOFTEST
111. REFERENCES
P a g e
iii
v i
v i i
1
3
3
5
9
12
13
26
27
28
30
39
45
47
50
55
V
FIGURES
Figure
1
2
Page
6 Depos i t i on Sampl er
Radioactive Corrosion Product Monitoring Pene tr a t i on s 11
15
16
17
18
19
20
21
22
23
24
Optical Micrographs of Specimen 2E( 304-C-1)
Optical Micrographs of Specimen OE(304-C-3)
3
4
5
6
7
8
9
10
11
12
13
Op t i cal Micrographs of Specimen l F ( 304-C-2)
Optical Micrographs of Specimen 3E(316-C-3)
Optical Micrographs o f Specimen 4F( 316-C-2)
Optical Micrographs of Specimen 5F(316-C-l)
Op t i cal Micrographs o f Specimen 6F( 316-W-1)
Optical Micrographs of Specimen 7E(316-W-2)
Optical Micrographs of Specimen 8E( 304-W-1)
Optical Micrographs of Specimen 9E(304-W-2)
Photographs Showing Change in Distribution of Sod i um Accumul a t i on on Condenser P1 a te 32
R u n 29 Apparatus and Results of the Sodium Vapor Deposition on Parallel Plates
14 34
Apparatus f o r Study of Sodium Vapor Deposition i n Pipes
15 37
Deposition of Sodium in 3/4;in. Tubing from Flowing Argon Stream
16 39
Velocity Profiles f o r Mercury Next to a Heated P1 ate
17 42
Temperature Profiles f o r Mercury Next to a Heated P1 ate
18 43
Packing Effects on Natural Conduction Heat Transfer from a Vertical Heated Plate
19 44
vi
TABLES
Tab1 e
1 c
2
3
4
5
6
7
a 9
10
Concentrations o f Contamination Deposits on ST-1A Deposi ti on Sampl er Surf aces
Carbon Concentration o f Metal1 ography Specimens
FFTF Si 1 icon Analysis Summary
Sodium Vapor Deposition on Fla t Plate Condenser Inclined a t 90°
Sodium Vapor Depos i t ion on Parallel Plate Baffles
Sodium Deposition i n Cover Gas P i p i n g Tests on 3/4-in. Tub ing w i t h Gas Flow o f 100 cc/min
MIST P1 uggi ng Temper a t ures
Detector l/GLASS 1 Ratios vs A/C Position
Detector 2/GLASS 2 Ratios v s A/C Position
Gama Ray Reduction Factor Comparisons vs A/C Position and Detector
Page
7
25
29
31
35
46
52
53
54
38
v i i
SODIUM TECHNOLOGY PROGRESS REPORT
JULY - SEPTEMBER 1980
MANAGEMENT SUMMARY
Sodium technology programs prov ide the t e c h n i c a l bas i s f o r safe and e f f i c i e n t use o f sodium as a reac to r coolant .
broad base o f technology, t h e HEDL programs p rov ide support f o r Fast F lux Test F a c i l i t y s t a r t - u p and operat ion. Overa l l program o b j e c t i v e s are t o e s t a b l i s h sodium and cover gas p u r i t y requirements; develop and demonstrate
p u r i f i c a t i o n , sampling, and analys is methods, components, and instrumen- t a t i o n ; c h a r a c t e r i z e mass and a c t i v i t y t r a n s p o r t e f f e c t s i n r e a c t o r systems;
develop r a d i o a c t i v i t y c o n t r o l methods requ i red t o pe rm i t con tac t maintenance on t h e p r imary heat t r a n s p o r t system; and develop a decontamination process
f o r removing r a d i o a c t i v i t y f rom pr imary system components r e q u i r i n g main-
tenance and reuse.
I n a d d i t i o n t o developing a
Dur ing t h i s r e p o r t i n g per iod, t h e f o l l o w i n g were accomplished:
. Two p r o t o t y p e r a d i o n u c l i d e t raps have each f i n i s h e d two cyc les i n
Source Term Contro l Loop 3 (STCL-3) was being gama-scanned a t 60 se lected l o c a t i o n s t o determine r a d i o n u c l i d e d i s t r i b u t i o n i n sodium loops w i t h o u t r a d i o n u c l i d e t raps.
An 8000-hour t e s t was completed t o evaluate r a d i o n u c l i d e depo- s i t i o n and pene t ra t i on i n t o AIS1 304 and 316 s t a i n l e s s s tee l s .
Based on p o t e n t i a l t r a n s p o r t of 58C0 from the core reg ion, an improved c o n f i g u r a t i o n f o r r a d i o n u c l i d e t raps would have n i c k e l c o a t i n g on o n l y the gas plenum r e g i o n o f f u e l p ins.
Planning cont inued f o r t h e s u r v e i l l a n c e o f r a d i o a c t i v i t y b u i l d u p i n t h e FFTF heat t r a n s p o r t system.
EBR- 11.
.
.
.
.
. Examination o f t h e depos i t i on sampler f rom the E B R - I 1 Breached Fuel Test F a c i l i t y was completed. deposited i n t h e sampler was associated w i t h f u e l p a r t i c u l a t e s .
Most o f the contaminat ion
1
0
0
e
0
A t e s t w i t h an improved cesium t r a p design was s t a r t e d i n t h e F i s i o n Product Transpor t Loop.
Laboratory equipment was s e t up f o r i n v e s t i g a t i o n of oxygen-s i l icon chemist ry i n sodium, as p a r t o f the program t o charac ter ize and c o n t r o l p a r t i c u l a t e fo rmat ion i n h igh temperature sodium systems.
A data base was es tab l i shed dur ing 800OF t e s t i n g o f FFTF, i n p repara t ion f o r s u r v e i l l a n c e o f s i l i c o n e f f e c t s i n FFTF systems dur ing f u l l power operat ion.
Sodium f r o s t t e s t s were completed t o charac ter ize depos i t ion p a t t e r n and r a t e s w i t h f l a t p l a t e condensors and w i t h vary ing i m p u r i t y l e v e l s i n t h e argon cover gas. Add i t i ona l t e s t s were s t a r t e d t o determine p lug fo rmat ion t ime and cond i t i ons i n cover gas l ines , bo th heated and unheated.
Cold t r a p performance was evaluated dur ing the f i n a l Maximum Isothermal Sodium Temperature t e s t p e r i o d on FFTF.
Studies were completed on ef fects of mesh packing on na tu ra l convect ion i n a cold t r a p c r y s t a l l i z e r .
I n s t a l l a t i o n and acceptance t e s t i n g of the Fuel F a i l u r e Mon i to r ing System on FFTF were completed.
Responses o f two absorber /co l l imator devices were measured, and a mod i f i ed gamma r a y sub t rac t i on device was tes ted on t h e E B R - I 1 Fuel F a i l u r e Mon i to r i ng equipment p roo f tes t .
1
2
2. Accompl ishments
I , RADIOACTIVITY CONTROL TECHNOLOGY W. F. Brehm
The R a d i o a c t i v i t y Con t ro l Technology Program i s developing technology t o p r e d i c t , measure, c o n t r o l and remove r a d i o a c t i v i t y f rom sodium-cooled
r e a c t o r systems. Act1 vated co r ros ion products , fue l p a r t i c u l a t e s , t r i t i u m
and f i s s i o n products species are o f i n t e r e s t . The complex i ty and magnitude o f r a d i o n u c l i d e t r a n s p o r t and depos i t i on r e q u i r e i n v e s t i g a t i o n and develop-
ment o f severa l c o n t r o l methods. Th is q u a r t e r ' s r e p o r t descr ibes progress i n r a d i o n u c l i d e t r a p development, decontamination process development,
examinat ion o f depos i t i on and d i f f u s i o n specimens, cesium t r a p t e s t i n g , and r a d i a t i o n l e v e l c a l c u l a t i o n s .
A. RADIONUCLIDE TRAP DEVELOPMENT J. C. McGuire and W. F. Brehm
1. O b j e c t i v e
The o b j e c t i v e o f t h i s program i s t o develop a method f o r removing long-
l i v e d g a m a - e m i t t i n g rad ionuc l i des f rom LMFBR p r imary loop sodium t o c o n t r o l
d e p o s i t i o n i n areas where maintenance i s required.
EBR-11 Radionucl ide Traps 3 and 4 (X-356 and X-357) have each completed t w o i r r a d i a t i o n cyc les w i t h o u t i nc iden t . d r i v e r pins, w i l l be removed du r ing Run 112, disassembled, one p l a t e d dumny
p i n removed, and t h e experiment r e c o n s t i t u t e d f o r f u r t h e r i r r a d i a t i o n . Examination o f t he removed p i n w i l l p rov ide e s s e n t i a l i n f o r m a t i o n on weight
loss, n i c k e l corros ion, 58C0 generation, downstream e f f e c t and 54Mn g e t t e r - ing. Specimens o f FFTF f u e l c ladd ing were success fu l l y sput ter -coated w i t h
n i c k e l .
N i cke l th icknesses o f 0.0003 in. and 0.003 in. have been appl ied.
X-357, t h e t e s t of n i c k e l - p l a t e d
. . The c o a t i n g appears t o be d u c t i l e , smooth and very adherent.
3
Source Term Control Loop 3 (STCL-3) has operated w i t h o u t a radionuclide trap f o r 9000 hours. ac t iv i ty to determine ac t iv i ty movement i n the absence of a t rap . The scans to date show that ac t iv i ty has not only b u i l t up i n the cold leg, b u t t h a t i t has moved through the system. Cobal t i s now seen i n a l l parts of the l o o p w i t h a significant concentration i n the area where sodium i s being heated before entering the hot sample stringer. This indicates that cobalt i s present in the sodium stream throughout the loop, and t h a t i t deposits preferentially in the hot zone, even af ter passing through a cooler area.
We are now completing a detailed gamma scan of loop
In an investigation of a1 ternative approaches fo r instal l ing radio- nuclide traps i n future reactors, a single 28-in. diam x 24-in. l o n g rolled nickel sheet trap installed i n the outlet pipe of each primary c i rcu i t w i l l provide over twice the getter area of a conventional trap unit mounted i n every core assembly.
3. Future Work
Design a trap u n i t w i t h 0.060-in. spacing between layers fo r low pres- sure drop .
Test the properties of sputter-coated cladding.
B. FISSION PRODUCT AND FUEL TRANSPORT BEHAVIOR AND CONTROL R . P. Colburn , H. P. Maffei and M . B. Hall
1. Objective
The objectives of this program are: 1) t o determine f iss ion product and fuel particulate transport kinetics and deposition patterns i n LMFBR primary heat transport systems, 2 ) t o determine impacts t h a t transport and deposition of these radionuclides will have on plant maintenance, 3) to
4
develop methods to monitor and control their deposition, and 4 ) t o provide i n terpret i ve i nf ormat i on for the Run-Beyond -C 1 add i ng-Breach ( R B C B ) Program.
c 2. Accompl i s hmen t s 1
Examination of the deposition sampler, ST-lA, used i n the Breached Fuel Test Fac i l i ty (BFTF) a t EBR-I1 during the XY-2 breached fuel t e s t was com- pleted. This examination included disassembly of the sampler, gama scan- n i n g of the individual pieces and characterizations of the deposits. Analysis of these data is continuing. The sampler i s i l lus t ra ted schema- t i c a l l y i n Figure 1. A detailed description of the sampler, i t s exposure conditions and a sumary of preliminary examination f i n d i n g s were given i n References 1, 2 and 3. I t was previously noted t h a t over 80% of the total contamination ac t iv i ty deposited i n the sampler was deposited on the f i l t e r . Further analysis indicates over 90% of the total was associated w i t h the f i l t e r , w i t h 40% of that material contained i n the loose debris that accumulated around the standpipe below the f i l t e r (Sample Position 1 i n Figure 1).
The concentrations of some of the major contaminants on various sur- faces are shown i n Table 1. The calculated fuel and f ission product inven- to r i e s in the breached pin a t the time of cladding fa i lure are also shown, The ratios o f Pu to U i n the deposits on the f i l t e r and around t h e stand p ipe
below the f i l t e r (Sample Positions 1, 2 and 3 ) were similar to the r a t i o in the source p i n . These data, together w i t h the general coincidence of alpha and gama ac t iv i ty dis t r ibut ions on a microscopic scale on the f i l t e r sur- face, suggest that most of the contamination transport of these species was by fuel par t iculate entrainment i n the sodium.
The contaminants on the inner surface of the top piece (Sample Posi- t ion 4 ) represent the deposition downstream from the f i Iter. on the outer surface of the top piece represents deposition a t the out le t of the unfiltered flow path. surface fo r similar mass transfer conditions indicates substantial removal
Contamination
The much lower concentrations on the inner
5
t 6 cm
I IST
84 CIp7
2N D CUT
22 crn
[ SODIUM 1 FLOW
HEDL 8007-028.1
FIGURE 1. Deposition Sampler.
6
TABLE 1
CONCENTRATIONS OF CONTAMINATION DEPOSITS ON ST-1A DEPOSITION SAMPLER SURFACES
Sample Locat ion Fuel (vqm/cm2)
- No. D e s c r i p t i o n Pu U
2 F i l t e r - Lower End 0.59 1.23
3 F i l t e r - 25 cm from Lower End 1.31 4.25
4 Top Piece I D 0.0001 0.014
5 Top Piece OD 0.0091 0.022 Ring 35 0.014 0.027
6 Outer Casing I D 0.013 0.028
7 Outer Casing OD , 0.0008 0.0046
1 Loose Deposits near (pgml ( w m )
Base o f Standpipe 400 1400
0 0 Fuel Pin* 16.8 52.3
F i s s i o n Products (pCi/cm2)
9 5 ~ r
54.0
68.6
0.27
2.29 2.25
2.66
0.23
(uCi)
57 35
( C i )
186
141ce
13.90
28.51
1.36
1.29 0.41
0.71
0.81
(pCi)
6239
( C i )
320
144ce
2.15
3.52
0.017
0.08 0.12
0.11
0.006
(uCi)
967
( C i )
39.7
103R u
6.35
8.86
0.19
( C i )
1501
68.2
*Tota l q u a n t i t y i n t h e f u e l p i n a t t ime o f breach *Not determined
7
Q of these contaminants by the f i l t e r . Similarly, a comparison of the deposit concentrations on the inner and outer surfaces o f the outer casing (Sample Positions 6 and 7 ) re f lec ts changes i n the contamination concentration in the sodium stream. sodium during the i n i t i a l upward f low through the sampler. They correspond ?
well w i t h the concentrations found on the deposition rings on the opposite annular wall. The concentrations on the outer surface, reflecting deposi- t i on from the sodium stream returning from the upper end of the BFTF, were much lower, suggesting that substantial deposition of these species occurred in the upper end of the BFTF. larger concentration on the outer surface. This may be explained by a transport mechanism i n which some of the 141Ce was released from the breached pin as i t s volat i le short-lived precursor 141Cs ( T ~ , ~ = 25 s) . While existing as a Cs species, i t tends to remain dissolved i n the sodium and not depos i t on surfaces .
deposit rapidly and once deposited, decays in place to 141La and 141Ce. This type of transport and deposition behavior was observed for 137Cs-137Ba in flowing sodium systems. ( 4 ) downstream concentrations of 14'Ba-14'La observed a t the upper end of the BFTF. the upper end of the BFTF d u r i n g a af ter i t s removal from the reactor. Subsequent decay prior t o the disassembly prevented accurate dis t r ibut ion measurements d u r i n g the detailed exami na t i on.
The inner surface re f lec ts the deposition from the
14'Ce was a notable exception, showing a
However, a f t e r decay to 14'Ba, i t t e n d s to
A similar mechanism could explain the large
These re la t ive ly large concentrations of 140Ba-140La were observed at ama scan of the f a c i l i t y two weeks
A second deposition sampler tes t (ST-1B) was started i n E B R - I 1 d u r i n g Run 108 i n conjunction w i t h the XY-5 breached fuel tes t . The tes t pins contain h i g h b u r n u p (14 at .%) mixed oxide fuel . t ical to the previous u n i t (ST-1A). No p i n breaches were detected through the middle of R u n 109. Two additional sampler units were fabricated and shipped to EBR-I1 to be used i n future breached fuels tes t s i n the BFTF.
The ST-1B sampler i s iden-
8
A cesium trap test was started i n the Fission Product Transport Loop w i t h an improved trap design t h a t is expected t o achieve lower Cs con- centrations i n the sodium and to make more e f f ic ien t use of the trap packing.
3. Future Work
L Complete analysis of ST-1A deposition sampler data and issue topical report.
Examine the ST-1B sampler at the conclusion of the XY-5 RBCB t e s t .
Perform two additional deposition sampler t e s t s in the BFTF.
Complete Cs t r a p t e s t in FPTL.
C. FFTF HEAT TRANSFER SYSTEM RADIOACTIVITY SURVEILLANCE H. P. Maffei
1. Objective
Maintenance operations for any nuclear plant are s ignif icant ly affected by radiation levels in equipment ce l l s . expected cel l radiation levels must be available during plant startup t o f a c i l i t a t e planning and designing for maintenance. Accurate r ad ia t ion level
predictions wi l l answer the questions of whether plants should be designed for "hands-on" or remote maintenance.
Reasonably accurate predictions of
2. Accompl ishments
Significant progress was made in predicting activated corrosion product b u i l d u p i n sodium-cooled reactor systems. the heat transport system (HTS) need t o be validated dur ing the startup of the FFTF. Without such validation, present calculated levels must be con- si dered "best e f for t" predict ions, with future maintenance techniques
These calculated predictions for
9
based on these ca l cu la t i ons . Ac tua l measurements of r a d i a t i o n l e v e l s w i l l
a l l o w s e l e c t i o n o f t h e c o r r e c t maintenance techniques p r i o r t o need.
Dur ing FFTF cons t ruc t ion , f i v e penet ra t ions were made i n t h e opera t ing f l o o r over HTS C e l l 3 f o r mon i to r i ng r a d i o a c t i v e co r ros ion products w i t h i n t h a t c e l l . These pene t ra t i on p o s i t i o n s are show i n F igure 2.
t i o n s 1 and 2 are p o s i t i o n e d over t h e pr imary sodium hot leg. i s over t h e crossover p i p i n g between t h e pr imary pump and heat exchanger, w h i l e Penet ra t ions 4 and 5 w i l l moni tor t h e c o l d l e g p i p i n g and check valve,
respec t i ve l y . Each pene t ra t i on i s a 2- in . diameter ho le through the concrete ope ra t i ng f l o o r . The leng th o f each hole i s %7 ft except f o r Penet ra t ion 3 over t h e crossover p ip ing , which i s 4 f t i n length. The holes
w i l l supply a c o l l i m a t e d beam o f r a d i o a c t i v i t y f rom an area o f ‘ ~ 3 2 0 crn2
(50 in.*) o f p ip ing .
Penetra-
Penet ra t ion 3
C a l i b r a t i o n o f the penet ra t ions and count ing equipment was p rev ious l y
r e p or t e d . (5) I n o rder t o ‘ cor re la te the n u c l i d e concentrat ion, which w i l l
be measured a t t h e t e s t ho les w i t h actual r a d i a t i o n exposure l eve l s , addi- t i o n a l ins t rumenta t ion w i l l be requi red. I o n i z a t i o n - t y p e r a d i a t i o n l e v e l de tec tors have been purchased f o r i n s t a l l a t i o n i n HTS C e l l 3. t h e inst rument w i l l a l l ow i n s t a l l a t i o n o f on l y the i o n i z a t i o n probe i n t h e
c e l l , thereby avo id ing r a d i a t i o n damage t o t h e inst rument dur ing r e a c t o r
power ,operation. Two probes w i l l be i n s t a l l e d i n c lose p r o x i m i t y ( ~ 1 m )
t o t h e p ip ing . Penet ra t ion 5. I n order t o ensure long probe l i f e , t h e inst ruments w i l l be k e p t w i t h power o f f u n t i l t he 24Na has decayed f o l l o w i n g power shutdown.
The design o f
One probe w i l l be under Penet ra t ion 1 and the second under
D. RADIATION LEVELS I N FFTF HTS CELLS
W. F. Brehm
1. Ob jec t i ve
The o b j e c t i v e o f t h i s work i s t o use t h e l a t e s t a v a i l a b l e n u c l i d e
re lease data and FFTF parameters t o c a l c u l a t e r a d i a t i o n l e v e l s f o r rad io - a c t i v e m a t e r i a l t ranspor t .
10
A
FIGURE 2: Radioactive Corrosion Product Monitoring Penetrations.
2. Accompl i shmen t s
I n the l a t e s t two quarterly reports ( 2 9 3 ) estimates were made of radia- t i on levels at 36OoC (68OoF), 316OC (60OOF) FFTF core in le t temperatures, and a t 36OoC core in le t w i t h radionuclide traps installed. the radionuclide trap used a 0.0076-mm (0.3-mil) thick coating of nickel as the trap material, which coated the ent i re length of the fuel pin. question was raised of 58C0 release and transport from the reaction 58Ni(n,p) Co and subsequent corrosion.
One concept of
The
58
The situation can be analyzed as follows: The equilibrium radiation levels in FFTF hot leg and cold leg sections of the HTS cell due to !j8Co
are 0.08 and 0.06 R/h, respectively. T h i s material comes almost ent i re ly from the corrosion of material i n the core (fuel s tack) region of the p i n , s ince the 58Ni(n,p) Co r e a c t i o n i s a h igh energy t ransmutat ion, which
occurs only i n the core region and not i n the f iss ion gas plenum region of the fuel p i n . The fuel cladding s t a r t s irradiation exposure a t 1.12% nickel; leaching of the nickel by sodium reduces the nickel concentration a t the surface to as l i t t l e as 2% (hence reducing the potential for 58C0 production and transport).
potential for 58C0 transport, if the ent i re fuel p i n i s nickel coated, would be a t l eas t 100/12 = 8.3 times as h i g h , and perhaps 100/2 = 50 times as h i g h . T h i s release would lead to radiation levels o f a t least 0.66 R / h i n the h o t leg and 0.50 R/h i n the cold, possibly much higher. levels, added to the 6oCo and (reduced) !j4Hn levels, would s t i l l resu l t in radiation levels at l eas t 1 R/h.
58
T h i s f a c t was accounted fo r by K u h n ( 6 ) i n his original calculations of radiation level; and i n subsequent estimates. ( 2 9 3 ) The
Such radiation
Therefore, we recommend that nickel coating of the f iss ion qas plenum region only be considered fo r this concept of radionuclide t raps . coating i n that region will produce negligible 58C0.
Nickel
12
n 3. Future Work
The temperature and flux parameters used i n Reference 6 were 1974 values. changes are present that would affect radiation level estimates.
These will be compared w i t h the l a t e s t data to see if significant
E. DECONTAMINATION OF BREEDER REACTOR COMPONENTS R. P. Anantatmula, J. M . Lu t ton , S. J. Bos and M. B. Hall
1. Objective
The objective of this ac t iv i ty i s to develop and demonstrate decontami- nation processes t h a t will permit contact maintenance and requal i f icat ion of breeder reactor primary system components.
2. Accomplishments
Test DECON-I, a study of radionuclide deposition and penetration i n t o AISI 304 and AISI 316 s ta inless s tee ls was completed. The s ta inless steel t e s t specimens were downstream from the radionuclide source a t a tempera- ture of 534OC and were exposed for a total time period of 8000 h i n Source Term Control Loop 3 (STCL-3). irradiated AISI 316 s ta in less s teel kept in the 549% hot leg of the pumped AT l o o p (STCL-3) ups tream from t h e test s p e c i m e n s . T h i s arrangement
i s assumed to simulate the temperature drop from reactor out le t to a hot leg pump. Two specimen arrangements were used: to a h i g h velocity sodium flow of 3.5 m/s (11 f t / s ) , the other perpendicular
The radionuclide sources were pieces of
one w i t h the coupons parallel
to the flow, a t a nominal velocity of 0.3 to 0.6 m/s (1 to 2 f t / s ) . ( 7 )
The ac t iv i t i e s of the radionuclides deposited on the specimens were counted w i t h a Ge-Li detector and a mu1 ti-channel analyzer, and corrections were applied fo r detector efficiency and geometry. Incremental radio- chemical analysis for the d e p t h dis t r ibut ion of 54Mn and 6oCo was also performed on selected specimens. 54Mn diffusion coefficients measured from the analysis of Phase I (2500 h ) and Phase I1 (4500 h ) specimens were
13
repor ted e a r l i e r . ( 8 ) O p t i c a l metal lography o f as-received specimens was
also repor ted. A t t he complet ion o f t e s t DECON-I, t he t e s t specimens were weighed and counted, and p o s t - t e s t meta l lography was performed on 4000-h specimens encompassing a l l heats o f t he A I S I 304 and A I S I 316
ma te r ia l s . Incremental radiochemical ana lys is i s a l so c u r r e n t l y be ing
performed on a few se lec ted specimens.
O p t i c a l micrographs o f cas t and wrought A I S I 304 and A I S I 316 s t a i n l e s s
s t e e l exposed f o r 8000 h a t 534OC are presented i n F igures 3 through 12. D i f fe ren t heats o f the m a t e r i a l s had d i f f e r e n t carbon concentrat ions. Table 2 l i s t s the specimens examined by o p t i c a l metal lography w i t h t h e i r
carbon compos i t i on s .
As mentioned i n t h e prev ious q u a r t e r l y repor t ( ' ) , t h e amount o f f e r r i t e i s more i n AISI 316 cas t ma te r ia l than i n AISI 304 cas t s tee l c o n t r i b u t i n g t o a l a r g e r l a t t i c e d i f f u s i o n c o e f f i c i e n t f o r 54Mn.
p o r o s i t y can be seen i n a l l the cas t m a t e r i a l s and i s exempl i f ied by l a r g e
ho les i n specimen OE (F igure 4).
b ide, near t h e sodium-exposed sur face o f a l l t h e cas t mater ia ls . p r e c i p i t a t i o n seems t o have a c t u a l l y s t a r t e d a t t he f e r r i t e - a u s t e n i t e i n t e r -
face, and p r e c i p i t a t i o n cont inued i n t o the f e r r i t e is lands. A small amount of carb ide p r e c i p i t a t i o n was no t i ced a t t h e a u s t e n i t e - f e r r i t e i n t e r f a c e of
t he as-received ma te r ia l s .
t rans format ion o f f e r r i t e .
Cast ing
There i s p r e c i p i t a t i o n , presumably car -
Carbide
Sodium exposure a t 534OC f o r 8000 h l e d t o
The wrought s t a i n l e s s s t e e l s genera l l y d isp layed equiaxed g r a i n Exposure t o 534OC sodium f o r 8000 h s t r u c t u r e w i t h anneal ing twins.
r e s u l t e d i n carb ide p r e c i p i t a t i o n around g r a i n boundaries and a l so w i t h i n
t h e gra ins . In a d d i t i o n t o carbides, Specimen 9E (F igure 12) had s t r i n g e r -
type i nc lus ions . The amount o f carb ide p r e c i p i t a t i o n genera l l y seems t o be cons is ten t w i t h t h e amount of carb ide present i n the a l l o y . There are f i n e
unresolved p r e c i p i t a t e s a t 1000~ m a g n i f i c a t i o n w i t h i n the aus ten i te g ra ins . I n add i t ion , specimen 8E w i t h 0.08 w t % carbon has l a r g e p r e c i p i t a t e s w i t h i n
some aus ten i te g ra ins . These p r e c i p i t a t e s were no t i d e n t i f i e d . Some or a l l
14
( b ) 30 urn C 1
FIGURE 4. O p t i c a l Micrographs o f Specimen OE (304-C-3).
16
FIGURE 5. Optical Micrographs o f Specimen 1 F (304-C-2).
1 7
FIGURE 6. Optical Micrographs o f Specimen 3E (316-C-3).
18
( b ) c 30 ptn I
F I G U R E 8. Optical Micrographs o f Specimen 5F (316-C-1).
20
(a 1 1 120 pm I
FIGURE 9. O p t i c a l Micrographs o f Specimen 6F (316-W-1).
2 1
F I G U R E 10. Optical Micrographs ' o f Specimen 7E (316-W-2).
22
FIGURE 11. Optical Micrographs o f Specimen 8E (304-W-1).
23
FIGURE 12. Optical Micrographs o f Specimen 9E (304-W-2).
24
TABLE 2
CARBON CONCENTRATION OF METALLOGRAPHY SPECIMENS
SamPle No. Ma te r ia l *
2E OE 1F
3E 4F
5F
6F
7E 8E
9E
304-C- 1 304-C- 3 304 -C -2 316 -C-3 316-C-2 316-C-1
316-W-1
317-W -2 304-W-1
304-W-2
*C - Cast; W - Wrought
o f these p r e c i p i t a t e s may be carb ides t h a t
p a r t i c l e s . Al though i t has been theor ized
W t % Carbon
0.09 0.07 0.05 0.06
0.05 0.08
0.04 0.07
0.08
0.03
have agglomerated t o l a rge -s i ze
i n the l i t e r a t u r e (lo t h a t
sigma-phase p r e c i p i t a t e s are favored i n A I S 1 304 SS w i t h a h igh carbon
content, t h e sodium-exposure temperature o f 534OC i s no t h igh enough t o promote the d i f f u s i o n o f s u b s t i t u t i o n a l elements l e a d i n g t o the f o r m a t i o n o f
sigma phase.
As p a r t o f t he decontamination s tud ies, t h ree p i l o t p l a n t runs were
made t o evaluate t h e on - l i ne co r ros ion meter.
ve ry we l l dur ing one of the runs as compared t o t h e e lect rochemical c e l l .
However, t r o u b l e was experienced i n t r y i n g t o r e s t a r t t h e opera t ion a f t e r t h e decontaminat ion s o l u t i o n was changed. The decontaminat ion s o l u t i o n
seemed t o be concent ra t ing over a p e r i o d o f t ime; and t h e r e c i r c u l a t i n g pumps were leak ing, presumably due t o a c i d a t tack . The pump seals have been
rep1 aced.
The co r ros ion meter performed
25
3. Future Work
Comp 1 e te t h e ev a1 u a t i on o f i nc remen t a 1 chemi c a 1 and r a d ioc hemi c a 1
ana lys i s data and gamma coun t ing data and prepare a f i n a l i n t e r p r e t a t i o n of r a d i o n u c l i d e depos i t i on on s t a i n l e s s s tee l s .
F. FFTF SUPPORT J. M. L u t t o n and S. J . Bos
1. Ob jec t i ve
The o b j e c t i v e o f t h i s program i s .I provic ethnical suppor i n sodium removal f o r FFTF.
2. Accomplishments
A t h i r d c o n t r o l rod d r i v e mechanism was cleaned i n t h e p i l o t p l a n t and
re tu rned t o Eng i neer i ng .
Par ts f rom a f a i l e d per iscope were sent t o us f o r c lean l i ness evalua- t i o n . l u b r i c a n t s was developed and used t o c lean s i x teen long sect ions and
numerous small pieces.
A c lean ing technique f o r removing r e s i d u a l g r a p h i t e from thread
26
11. SODIUM SYSTEMS TECHNOLOGY
J. J. McCown ( FF058, FOOOl, F0003)
Sodium Systems Technology programs cover development of methods for sampling, monitoring and controll ing impurities i n sodium and cover gas i n experimental loops and on sodium-cooled reactors. The programs include Fuel Failure Monitoring studies f o r the detection and location of elements containing cladding breaches.
To ensure that the FFTF and subsequent sodium-cooled reactors operate u s i n g sodium and cover gas of adequate purity, methods f o r sampling and on-line monitoring of impurities were developed and tested on sodium f a c i l - i t ies. Continuous on-line cover gas monitoring as well as gas tagging methods were established for fuel f a i lu re monitoring purposes.
The major program emphasis is upon laboratory studies on sodium f r o s t , preparation for laboratory studies of s i l icon control by chemical inter- actions w i t h other sodium impurities and f ina l loop checkout of small oxygen, hydrogen and carbon meters as inserts i n the Multipurpose Sampler. Technical support continued to be provided i n the areas of sodium and cover gas purification and characterization and f i ss ion product monitoring.
This section of the report discusses work underway i n Sodium Systems Technology including: par t iculate control and surveillance f o r effects i n FFTF; sodium f r o s t formation and control i n cover gas p ip ing; monitoring of FFTF chemistry d u r i n g MIST-3; modification and tes t ing of Fuel Failure Monitoring (FFM) equipment on EBR-I1 and completion of preparations on FFTF FFM systems prior to f u l l power operations.
27
A. SILICON COMPOUND PARTICULATE EFFECTS W. Yunker and D. Paine
1. Objective
The objectives of the Silicon Compound Particulate Effects program are t o determine 1) methods for control of the si l icon compound i n l i q u i d sodium systems and 2 ) effects o f the material on FFTF startup and operation.
Data from the preceding Flow Impedance Phenomena program proved that a sodium-silicon compound caused changes in the thermal/hydraulic performance of sodium heat transfer systems.
2. Accompl ishments
Results of Flow Impedance Phenomena t e s t s on the FIAS/PAL System (11 1 indicate that the oxygen impurity i n sodium and perhaps other chemical components interact w i t h si l icon and affect the mass transfer process. Since a cold trap i s the primary device in most sodium systems for control 1 i ng both oxygen and si 1 icon concentrations, some understanding of this interaction should be useful to control the si l icon concentration to a value that i s harmless to a specific system. Laboratory equipment is being assembl ed t e s t s w i 1 measur i ng co 1 1 ec ted pur i f i cat
and installed for conducting pot t e s t s du r ing FY 1981.
specific sodium impurities. has included 1) an iner t atmosphere glovebox, gas recirculation/ on t ra in , and gas atmosphere monitoring equipment for t e s t
These be designed to c la r i fy the FIAS resu l t s by controlling and
During this quarter, the equipment
preparations; 2 ) t e s t furnace power service and temperature measurement and control equipment, and a high vacuum pumping system for atmospheric control of the t e s t vessel.
The f i n d i n g s of the Flow Impedance Phenomena program (I1) are being applied to an FFTF observation program for i t s f u l l power operation. observations are to determine whether any effects on the plant are from
These
28
si l icon compound particulates. Operations, observations are planned of the main heat transport system flow resistance, subassembly flow and temperature dis t r ibut ions and the perfor- mances of the intermediate heat exchangers, the primary cold-trap heat exchanger and auxi l l ia ry p l u g g i n g meter. par t iculates is a lso b e i n g planned. from the data base being placed on the Boeing Computer Services, Richland UNIVAC computer. The necessary processing codes are being written. The MIST-I11 FFTF t e s t i n Augus t 1980 provided a useful opportunity t o col lect 30-1111 reference samples fo r s i l icon analysis and t o check the Auxiliary Plugging Temperature Indicator for operation i n the 350°F t o 8OO0F range. The recent s i l icon analyses are summarized i n Table 3.
In conjunction w i t h FFTF Engineering and
Overflow cup sampling for s i l icon Most of the data for analysis wil l be
TABLE 3
FFTF SILICON ANALYSIS SUMMARY
MI ST- I I I
Si 1 i con Reactor
Temperature
400 780
( O F )
Date
1/79 2/ 79 3/79 4/ 79
10/79 6/80
(Estimated) Solub i 1 i t y Si 1 icon
0 (wppm)
0.02 0.001
0.06 0.004 - + ( x 10)
PR EV IOUS ANALYSES
Concentration System (wppm)
Sec-1 0.4 PR I 0.2 Sec-3 0.3 Sec-2 c o . 1 PR I 0.1 Sec-3 0.5
29
3. Future Work
The tes t pot/furnace design will be completed and procurement started of components and materials.
Plans for si l icon particulate effects in FFTF will be completed and implemented d u r i n g the i n i t i a l two days of operation a t f u l l power.
B. SODIUM FROST TECHNOLOGY G. B. Barton and A. P. Bohringer
1. Objective
The purposes of this program are t o prevent sodium vapor deposits from a f f e c t i n g ope ra t ion of FFTF and to develop ope ra t ing and design c r i t e r i a f o r
liquid metals systems. Deposit Accumulation (SVDA) rates fo r forecasting maintenance requirements. The scope includes the effects o f sodium pool temperature, condenser sur- face configurations, cover gas impurities, p i p i n g configuration and tempera- ture, and gas flow rates .
Tests are intended for developing Sodium Vapor
2. Accompl ishments
F l a t plate condenser tes t s were continued to examine the effect o f higher oxygen concentration than previously reported, hydrogen impurity, and the effect of plating the condenser surfaces so that i t was wetted by sodium. The resul ts are sumnarized i n Table 4.
The ra te of evaporization and the ra te of accumulation on the condenser How- plate are only very s l igh t ly affected by changing the gas composition.
ever, the retention on the plate does vary w i t h the atmospheric and surface conditions of the plate. i n distribution and accumulation of the deposit.) viscosity of the molten sodium as i t piles up ( R u n 26).
(See Figure 13, which i l l u s t r a t e s the difference Oxygen increases the
The t in coating was
30
TABLE 4
SODIUM VAPOR DEPOSITION OF FLAT PLATE CONDENSER INCLINED AT 90'
Na Pool R u n (OCie;l;Fl Time a t No. Temp ( h )
24 538 1000 24
_.
25 538 1000 24
26 538 1000 24
27 538 1000 24
538 1000 24 W I- 28
Atmospheric Compos i t i o n
Ar 0.68 ppm H20
Ar, 23 ppm H2 7.5 ppm H20
Ar, HO ppm 02 0.62 ppm H20
Ar 0.67 ppm H20
Ar 0.65 ppm H20
Evapor i z a t i on Condensation Condenser Rate** Rate***
Inc l (0 ) . S u r f a c F (g/s. m2) (q/s.m2)
9 Used 0.218 0.0195
9 Used 0.210 0.0180
9 Used 0.215 0.0185
9 Tinned 0,214 0.0198
g Ag P la t ed 0.218 0.0171
Frac t ion Fraction of Condensate Effected on Remaining on
Condenser (%) Condenser (%)
35.5 31.4
33.9 30.9
34.1 42.1
36.7 36.5
31.1 53.8
*The condenser used fo r these experiments had been used f o r 9 previous t e s t s . The co l l ec t ion and removal of sodium leaves a t a rn i sh on t he sur face of the s t a in l e s s s t e e l . f l u x . The s i l v e r p l a t e was generated by using Rocdelle s a l t s mirror s i l v e r i n g so lu t ion . Both coatings were applied only t o the upper sur face .
***Condenser top sur face area = 221 cm2; a l l the sodium c o l l e c t e d on i t appears to have been from s e t t i n g o f mist p a r t i c l e s . Temperature d i s t r i b u t i o n on condenser p l a t e :
The t i nned sur face was generated by melting pure t i n u n d e r a so lde r ing
**Sodium container ID = 3.32 in. , and calculated sur face a rea = 55.85 cm2.
I n l e t end = 500 2 1 5 O F , middle = 402 2 8OF; o u t l e t end = 370 - + 8OF.
R u n 24 Run 25 View o f Condenser Top a t 9' Incline
Run 26 View o f Condenser Surface
R u n 27 R u n 28 Frost Test
FIGURE 13. Photographs Showing Change in Distribution of Sodium Accumulation on Condenser Plate. variables.)
(See Table 1 for operating condition
32
removed by the sodium and formed massive patches of an i n t e r m e t a l l i c com-
pound. coa t ing increased t h e w e t t i n g o f the condenser p l a t e by sodium and may have
increased the v i s c o s i t y s ince drainage was not as complete as on other t e s t s .
(See area a t l e f t center o f photograph o f Run 27). The s i l v e r
Three t e s t s were performed on a p a r a l l e l p l a t e b a f f l e system s i m i l a r t o t h e thermal b a f f l e s used i n var ious pieces o f equipment.
was g rea te r t o a l l ow examination o f a wider temperature range i n a s i n g l e
t e s t . The general apparatus i s shown i n F igu re 14 along w i t h p i c t u r e s o f
t h e b a f f l e s wi th t h e i r sodium accumulation, The data are s u m a r i z e d i n
Table 5 .
The p l a t e spacing
The f i r s t conc lus ion i s t h a t convect ive c i r c u l a t i o n o f m i s t i s t h e major sodium t r a n s p o r t mechanism. The f i r s t t e s t (No. 29) showed evidence
o f sodium r e f l u x i n g o f f t h e bottom p l a t e so t h e subsequent t e s t s were
shortened. Comparing t h e accumulation r a t e s ca l cu la ted f o r t he t h r e e runs, t h e r e does n o t appear t o have been s i g n i f i c a n t d i s t o r t i o n o f t he depos i t i on
p a t t e r n by r e f l u x i n g . The h ighe r evaporat ion r a t e s f o r t h e two s h o r t e r runs r e s u l t f rom t h e neg lec t o f t he evaporat ion o c c u r r i n g du r ing heatup and coo l -
down. I n the photograph through the viewport , P la tes 4 and 5 are v i s i b l e . P l a t e 4 i s j u s t below the l e v e l of the s i d e arm.
expanded gas volume around t h i s p l a t e increases the depos i t i on ra te .
It appears t h a t t he
On t h e lower two p l a t e s the sodium was molten; on the center one, par-
t i a l l y so; and on t h e upper two, it was a sponge.
A t t h e oxygen l e v e l tested, it appears evaporat ion i s s l i g h t l y reduced
over t h a t i n pure Ar, t he d e p o s i t i o n p a t t e r n i s s l i g h t l y modif ied, and a sma l le r f r a c t i o n deposi ts on t h e p la tes. With t h e b a f f l e c learance o f
0.42 in., convect ion r e a d i l y occurs. Whether t h i s c e l l i s go ing up one s i d e and down t h e o the r or i s laminar i s n o t c lea r , b u t t h e unsymnetr ical deposi t
on P l a t e 4 suggests t h e former.
The fo rma t ion of sodium vapor deposi ts i n pipes -- p a r t i c u l a r l y t he FFTF gas e q u a l i z a t i o n l i n e s and t h e reac to r vessel e x i t l i n e -- t h a t c o u l d
33
General View o f Apparatus View o f Upper Two Pla tes Showing Sodium Deposi t
Top View o f P la tes Bottom View o f P la tes Showing Small Amount o f Accumulated Sodium on Bottom of Bottom P l a t e
FIGURE 14. Run 29 Apparatus and Resu l t s o f the Sodium Vapor Depos i t ion on P a r a l l e l P la tes.
34
6
R u n No.
29
-
30
31
W Ln
R u n No.
29
-
30
31
TABLE 5
SODIUM VAPOR DEPOSITION ON PARALLEL PLATE BAFFLES
Na Pool Evaporation Bottom Pla te 2nd Plate Time a t AtmosDheric Total Rate Sod i urn Sod i urn
538 1000 5 Ar 21.03 0.209 249 480 2.12 0.424 157 315 1.54 0.308 0.30 ppm H20
0.40 ppm H20
0.40 ppm H20
538 1000 1.5 Ar 8.53 0.283 249 480 0.52 0.347 163 326 0.52 0.347
558 1000 1.5 Ar, 140 ppm 02 7.95 0.264 249 490 0.41 0.273 197 387 0.34 0.227
4th Plate Top P la t e Total Deposits 3rd Plate Temp e r a t u r e Sod i urn Temperature Sod i um Temperature Sod 1 um Sodium on Plates ( O C ) ( O F ) (9) (g/h) ( O C ) ( O F ) (9) ( g / h ) ( O C ) ( O F ) (9) 0 0 0 112 233 1.44 0.288 78 172 1.71 0.342 62 143 1.47 0.297 8.28 39.4
118 245 0.46 0.307 88 190 0.53 0.352 68 155 0.43 0.287 2.46 28.8
142 287 0.36 0.240 93 200 0.45 0.300 63 146 0.33 0.220 1.83 23.0
Dimensions: ( i n . )
Vessel Inner Diameter 3.84 Plate Diameter 3.00 Plate Spacing 2.5
Overall Height o f Vessel 20.5 Top Plate to Flane 5.
impede gas f l o w i s a quest ion o f concern. and t h e i r mode o f fo rmat ion are be ing examined on a l abo ra to ry sca le t o
provide understanding for control o f these deposits.
The character o f these deposi ts
The exper imental setup i s shown i n F igu re 15. The bas ic sodium
evaporator i s t h e same as t h a t used f o r t h e f l a t p l a t e condenser exper i -
ments. The photograph shows a g lass c o l l e c t i n g tube i n p lace f o r Run 35. This was used f o r v i s u a l observa t ion o f t he l o c a t i o n and d i s t r i b u t i o n o f the
deposi t . Runs 33 and 34 employed s t a i n l e s s s tee l tubing, 3/4 x 0.035-in. The tub ing was c u t i n t o lengths; t h e sodium conta ined i n it was then removed
and the q u a n t i t y determined.
The r e s u l t s are sumnarized i n Table 6 and F igure 16. Test 32 employed
a 3 - f t v e r t i c a l sec t i on o f 3/4- in. SS tub ing. The data are i n t e r p r e t e d as i n d i c a t i n g f l o w o f gas up the center o f the tube u n t i l near t h e t o p t h e f l o w
changes d i r e c t i o n i n a tee. Th is d i r e c t i o n change induces turbulence i n t h e gas t h a t c a r r i e s m i s t p a r t i c l e s t o t h e wa l l . Between t h e tee and t h e vapor t r a p the re i s a swagelok reducer f rom 3/4- in. t o 1/2- in. tub ing .
opening o f the smal le r sec t i on o f t h i s reducer was covered by the sodium
deposi t , bu t i t had no t stopped the gas f low.
The
The r e s u l t s f rom Tests 33 through 35 demonstrate t h a t sodium c o l l e c t i o n
Test 34 shows t h a t r a i s i n g the w a l l temperature above the i n t h e tube i s by s e t t l i n g o f m i s t p a r t i c l e s w i t h a very minor d i r e c t conden- s a t i o n o f vapor.
m e l t i n g p o i n t o f sodium reduces t h e c o l l e c t i o n on t h e wa l l and moves t h e
depos i t i on f u r t h e r downstream. Some r e f l u x i n g o f sodium f rom the heated
zone occurred.
Since it appears t h a t sodium depos i t i on i n cool o r c o l d p ipes i s
l a r g e l y a m i s t depos i t i on process, more knowledge i s needed o f t he genera-
t i o n and t r a n s p o r t o f m i s t as a f u n c t i o n o f sodium poo l temperature, cover gas p u r i t y , temperature grad ien t , f low r a t e ( v e l o c i t y ) and p i p i n g geometry. It i s planned t o conduct more experiments t o e luc ida te some e f f e c t s .
36
FIGURE 15. Apparatus f o r Study of Sodium Vapor Depos i t i on i n Pipes. ~e~ 8008649-3cn
Run No.
32
-
TABLE 6
SODIUM DEPOSITION I N COVER GAS P I P I N G TESTS ON 3 /4 - INCH TUBING WITH GAS FLOW OF 100 cc/min
Na Pool E v a p o r a t i o n Time a t Atmospher ic T o t a l Rate u& Temp (h) Composi t ion & jg/s.m2)
470 8 00 97 A r 23.9 ~ 0 . 1 ppm H20
0.01225
33 427 800 97 A r 26.84 0.01376 ~ 0 . 1 ppm H20
w M
34
35
427
427
800 97 Ar 22.86 ~ 0 . 1 ppm H20
800 96 A r 22.2 ~ 0 . 1 ppm H20
0.01172
0.01 150
Na” ( g j
0.38 0.0025 0.0029 0.0024 0.0029 1.5 1.4 1.1
0.015 1.6 2.6 0.32 0.15 0.055 0.020 0.019 0.012 0.00086 0.00097 0.00021 0.0076 0.0047 0.0016 0.0072
0.34 0.83 1.0 0.74 0.10 0.0091 0.020 0.049 0.0017 0.030
0.032 4.7 1.1 0.22 0.073 0.0022 0.015 0.022 0.0025 0.050
Na C o l l e c t i o n S e c t i o n Length Weiaht of
No.
1 6 2 6 3 6 4 6 5 6 6 6
Tee Vapor Trap
1 2 3 4 5 6 7 8 9
10 11 12 13 14 15 16
1 2 3 4 5 6 7 8 9
2-3/8
6-5/8
6-1/4
5-1/2
6
6 6 6 6 8 8-3/4 ELL
10-1/2 10
8 7 9 9 6
12 7
15
Vapor Trap
1 6 2 10 3 7 4 7 5 9 6 7 10 8 7-1/4 9
Vapor T r a p
( w t / i n . )
0.063 0.00042 0.00048 0.00040 0.00048 0.250
0.0063 0.29 0.39 0.053 0.024 0.0092 0.0033 0.0032 0.0020 0.00011 0.00011
0.00072 0.00047
0.043 0.12 0.11 0.082 0.017 0.00076 0.0029 0.0033
0.0053 ‘ 0.47 0.16 0.031 0.0081
0.0015 0.0030
Comnents
V e r t i c a l V e r t i c a l V e r t i c a l V e r t i c a l V e r t i c a l V e r t i c a l 90° change i n d i r e c t i o n
V e r t i c a l V e r t i c a l t o h o r i z o n t a l bend (50 r a d i u s ) H o r i z o n t a l , s t r a i g h t H o r i z o n t a l , s t r a i g h t H o r i z o n t a l , s t r a i g h t H o r i z o n t a l , s t r a i g h t H o r i z o n t a l , 900 bend H o r i z o n t a l , s t r a i g h t H o r i z o n t a l t o v e r t i c a l bend V e r t i c a l , s t r a i g h t V e r t i c a l , s t r a i g h t 90° elbow H o r i z o n t a l , s t r a i g h t H o r i z o n t a l , 45O bend Tee and reducer Vapor t r a p
(50 r a d i u s ) V e r t i c a l 2-3/4 i n . & 90° bend 5-1/4 i n . H o r i z o n t a l end o f heated s e c t i o n (350OF) H o r i z o n t a l end o f heated s e c t i o n (350OF) H o r i z o n t a l end o f heated s e c t i o n (35OOF) 90° bend t o v e r t i c a l V e r t i c a l 90° bend H o r i z o n t a l Union & reducer
V e r t i c a l , SS 90° bend, g l a s s H o r i z o n t a l , g l a s s H o r i z o n t a l , g 1 ass 90° bend, g l a s s S t a i n l e s s s t e e l , swagelok connector 90° bend, SS H o r i z o n t a l , SS Union & reducer
PIPE (in.) HEDL 8011-111.4
FIGURE 16. Deposi t ion o f Sodium i n 3/4-in. Tubing from Flowing Argon Stream. (Sodium pool temperature i s 427OC (800oF) w i t h cover gas f l o w r a t e a t 100 cc/min and v e l o c i t y a t 0.71 cm/s.)
C. COLD TRAP TESTING G. R . Bloom and J. R . Welty*
1. Objec t ive
The o b j e c t i v e o f t h i s program i s t o p rov ide t e c h n i c a l support f o r
design, procurement and opera t ion o f t h e FFTF and HEDL t e s t f a c i l i t y c o l d
t raps. t r a n s f e r f i l m c o e f f i c i e n t s were determined f o r s imulated c o l d t r a p heat
t r a n s f e r s u r f aces.
Crys ta l1 i z e r packing e f f e c t s on l i q u i d metal n a t u r a l convect ion heat
*Mechanical Engineer ing Department, Oregon State Un ivers i ty , C o r v a l l i s , OR.
39
2. Accompl i s hmen t s
Laboratory studies were performed t o determine the crystal l izer packing effect on sodium velocity and temperature generated by the natural convec- tion heating in the core region of a cold t r a p crystal l izer . by Humphreys and We1 ty('*) determined velocity profiles for mercury contacting a heated bare vertical plane. The original work w i t h the bare heated wall was extended from a Grashoff number (Gr*) of 10l1 t o 2 x 10l2. The data are presented as generalized plots of Nussult number vs Grashoff number.
Previous work
For a vertical heated plate the Grashoff number i s defined as:
where:
ql1 = heat f l u x from heated wall $ = thermal coefficient of volumetric expansion g = gravitational acceleration v = kinematic viscosity k = f l u i d thermal conductivity X = vertical distance along the plate
The Nussult number is defined as:
where:
h = fi lm heat transfer coefficient X = vertical distance along the plate k = f lu id thermal conductivity
40
Mercury is a liquid metal w i t h heat transfer properties that can be used to model heat transfer i n a sodium cold trap crystal l izer . Modeling i s accomplished by matching the Grashoff number of the mercury tes t system t o that typical of a "similar" sodium system. because velocity profiles can be measured experimentally while sodium velo- c i t y measurements w i t h hot wire anemometer methods are not possible. mercury temperature prof i le experiments are less expensive and easier to perform than similar sodium experiments.
63
Mercury studies are valuable
The
The velocity prof i le and temperature prof i le data were extended f o r the case of higher Grashoff numbers. laminar flow regime. The higher Grashoff number data now extend into the transit ional region between laminar and turbulent flow. was increased i n these experiments by increasing X ( the vertical distance a1 ong the plate) . f o u r t h power of the distance X .
Previously data were fo r the case of the
The Grashoff number
The Grashoff number increases proportionally to the
The velocity and temperature profiles for the mercury a t three d i f fe ren t Grashoff numbers are given i n Figures 17 and 18. were measured 27.3 cm from the bottom of the bare heated plate w i t h similar data being obtained a t 2.6 cm.
The prof i les
The mercury flow is concentrated into a narrow region w i t h the majority of the flow being w i t h i n 15 mn of the wall. The thermal boundary layer i s
also concentrated w i t h i n 15 mn of the heated surface. These resu l t s are simil ar to previously reported velocity profiles ( I3 ) for mercury obtained a t lower Grashoff numbers.
A generalized plot of Nussult number vs Grashoff number is presented i n Figure 19 where the e f fec ts o f cold trap c rys ta l l izer packing wire diameter are shown. wire cold trap packing having diameters o f 0.25 mn and 0.12 m. The woven wire packing density was varied to re ta in a constant specif ic surface area
The heated vertical plate was convered w i t h prototypic woven
41
HORIZONTAL DISTANCE FROM HEATER (mm) FIGURE 17. V e l o c i t y P r o f i l e s f o r k r c u r y Next t o a Heated Plate.
X = 27.3cm
0 Grx*= 7.34 x 1011
* Gr,*= 1.24 x 101*
0 Grx*= 1.92 x 1012
b
30.00
I I
X = 27.3 cm - Gr:= 7.34 x 1011
A Gr,*= 1.24 x 1012 I
0 GrXu= 1.92 x 1012 - -
-
-
-
-
- -..
HORIZONTAL DISTANCE FROM HEATER (mm) HEDL 8011-111.3
IGURE 18. Temperature Profiles for Mercury Next to a Heated Plane.
m.oo
65.00
- - - d
I I I I I I 1 I , I I I 0.00 5.00 10.00 15.00 20.00 25.00
40
30
3 Z
P P 20
10
I I 1 I I 0.25-mm DIAMETER PACKING -
- -
NO PACKING
-
I I 1 I I I I I I I I 1 1 4 6 8 10 12 14 16 18
HEDL 8011-111.2 Gr* x
FIGURE 19. Packing E f f e c t s on Natura l Conduction Heat T rans fe r f rom a V e r t i c a l Heated Plate.
Q . c>
2 3 3 o f 82 m /m i n t h e packed reg ion. The packing d e n s i t y was 0.33 kg/m f o r the 0.25-mn diameter w i r e packing and 0.2 kg/m f o r t he 0.12-mn diameter
p ack i ng . 3
The w i r e diameter was observed t o a f f e c t t he f i
c i e n t . The 0.25-mn diameter w i r e increased the heat
about 50% compared t o the 0.12-mn diameter packing.
c o e f f i c i e n t f o r t he 0.12-m diameter packing was s i m bare heated p l ate.
The e f f e c t s o f n a t u r a l convect ion heat t r a n s f e r
m heat t r a n s f e r c o e f f i -
t r a n s f e r c oef f i c i en t The heat t r a n s f e r
l a r t o t h a t f o r t he
have been t o increase
t h e amount o f heat t r a n s f e r and t o cause channel ing near the c o l d t r a p
c r y s t a l l i z e r w a l l . heat t r a n s f e r and increase f l o w channeling even f u r t h e r . The 0.12-mm diam- e t e r w i r e packing has l i t t l e o r no e f f e c t on the heat t r a n s f e r c o e f f i c i e n t
when t h e Grashoff number i s below 10l1 and does no t increase t h e f l o w
The 0.25-mn diameter w i re packing i s seen t o increase
channeling. t o a 0.2-kg/m d e n s i t y prov ides b e t t e r packing ma te r ia l .
These r e s u l t s demonstrate t h a t t h e 0.12-mm diameter w i r e packed 3
D. FFTF SODIUM SYSTEMS SUPPORT
G. B. Barton, G. R. Bloom, G. E. Meadows and W. Yunker
1. O b j e c t i v e
This program prov ides t e c h n i c a l and engineer ing support t o FFTF
operat ions, moni tors performance of FFTF p u r i f i c a t i o n and c h a r a c t e r i z a t i o n systems, and evaluates i m p u r i t y behavior i n t h e sodium and cover gas.
2. Accomplishments
I m p u r i t i e s i n t h e sodium and cover gas systems were fo l l owed and t h e
The bu lk sodium tem- i m p u r i t y behavior evaluated. Isothermal System Temperature (MIST) was conducted.
pe ra tu re was increased from 204OC (400OF) t o 42loC (790OF) f o r severa l days w h i l e the performance o f system components was evaluated. I m p u r i t y changes
During t h i s r e p o r t p e r i o d a t h i r d Maximum
@ 45
in the sodium and cover gas systems were of less magnitude than during the other two MIST tests. tes ts .
Table 7 gives the plugging temperatures for the MIST
TABLE 7
MIST PLUGGING TEMPERATURES
MIST I MIST I1 MIST I11 System 2/79 ( O C ) 8/79 ( O C L 7/80 ( O C )
Primary 167 145 146 HTS-1 146 % 135 < 127 HTS -2 146 Q 135 < 127 HTS-3 146.5 %147 < 127
The primary cold trap was increased from l l O ° C to 1 2 7 O C d u r i n g the 42loC operation. 1 1 6 O C during the 42loC operation.
The second cold traps were increased from l l O ° C to
Oxygen, hydrogen and carbon i n the primary sodium averaged 1.5 ppm 0, 0.05 ppm H and 0.6 ppm C. ar ies averaged 0.97 ppm 0, 0.04 ppm H and 0.033 ppm C . impurities i n the primary and secondary sodium core were w i t h i n acceptable 1 imi t s and were (5 ppm for each element.
The oxygen, hydrogen and carbon i n the second- Trace metal
Hydrogen in the primary cover gas increased from %3 pprn a t 204OC to a maximum of 54 ppm during the temperature increase to MIST. While a t MIST the hydrogen decreased to ~ 2 0 ppm and remained steady u n t i l the systems temperature was decreased to 204OC.
~4 ppm. Methane in the primary cover gas remained below the detectable l imit ("2 ppm) of the gas chronograph. Other impurities were (20 ppm i n the primary cover gas. No changes were detected i n the secondary cover gas sys tems .
The hydrogen then decreased t o
FFTF secondary loop cold trap pressure drops have continued t o increase to a maximum of about 5 psi. The pressure drop in the Loop 1 cold trap has
46
held f a i r l y constant and i s now at 4.7 psi a t 14 gpm sodium flow. The secondary Loop 2 and Loop 3 cold trap pressure drops increased from a maximum of 1.5 psi to near 3.8 psi a t 13 gpm sodium flow.
Q
The pressure d rop increases in Loops 2 and 3 are within the predicted value of 4 psi reported i n the las t quarterly. ( 3 ) The pressure drop rate increase accelerated d u r i n g the FFTF heatup t o near 78OoF d u r i n g MIST 111. The pressure drop increases are attr ibuted to redistribution of impurities deposited in the cold t rap c rys ta l l izers , and increasing the cold t rap in l e t temperature accelerated this process. The cold t r ap pressure drops are not expected to increase s ignif icant ly above 5 psi unless additional impurities are introduced into the secondary systems. In i t i a l startup impurity burdens have already been removed and deposited i n t o the cold trap. No additional burdens are expected in the secondary sodium systems except for system maintenance or the proposed steam generators.
Technical support was provided on cover gas monitoring in the areas of o i l vapor analysis, oxygen levels in RAPS, f ro s t formation i n unheated argon lines and f ros t behavior i n shield p l u g a n n u l i .
3. Future Work
Surveillance of sodium sampling and cover gas characterization and purification systems wil l continue. gas system impurities from sodium f i l l t o the f i r s t power r u n wi l l be made.
A study o f the FFTF sodium and cover
E. FFTF FUEL FAILURE MONITORING 0. V . Archer and F. E. Holt
1. Objective
This task provides technical support for the development, instal la t ion and startup of the Fuel Failure Monitoring System.
47
2. Accompl i s hmen t s
F a i l u r e Detec t ion Subsystem -- Technical ass is tance was provided t o
P1 ant Engineer ing and Operat ions t o rect i fy cu r ren t and expected problems and t o determine ac t ions t o be taken i n response t o F i s s i o n or Absorber Gas H i alarms.
Two problems were reso lved and recommendations made t o P lan t Engineer-
i n g t o prevent the LN2 f l o w r a t e t o the de tec tor Dewar f rom dropping sha rp l y and recorder power supp l ies f rom burn ing out.
dropped because the an t i -sp lash f i l t e r , a closed-end tube o f s in te red bronze i n s i d e the de tec to r Dewar, became f i l l e d w i t h debr is . The f i l t e r was
rep laced and the f l o w r a t e re tu rned to normal.
t h i s problem Engineer ing p lans t o make the recommended mod i f i ca t i ons t o the anti-splash device and venting o f the Dewar. One o f the channels on a
recorder f a i l e d because overheat ing caused i t s power supply t o burn out.
The LN2 f l o w r a t e
To prevent recurrence o f
Add i t i ona l v e n t i l a t i o n o f a l l recorders was recommended t o prevent recurrence and i s be ing imp1 emen ted.
Recommended responses t o F i s s i o n o r Absorber Gas H i a1 arms du r ing normal and i n i t i a l s t a r t u p operat ions were t ransmi t ted t o P lan t Operations.
The recomnended responses du r ing normal ope ra t i on s p e c i f i e d cover gas
a c t i v i t y concentrat ions t h a t would r e s u l t i n a r e a c t o r Scram, Power Descent, o r Operat ion a t Power. Dur ing the i n i t i a l ascent t o power and two-day power runs, i t was determined t h a t very l i t t l e f i s s i o n gas was present i n the f u e l
p ins. Consequently the recomnended ac t i on was t o cont inue opera t ion even i n the event o f an alarm and t o o b t a i n o ther samples.
F a i l u r e Charac te r i za t i on Subsystem (FCS) -- The mu1 t ichannel analyzer, mini-computer and da ta l i n k s t h a t make up the FCS were checked and o f f i -
c i a l l y turned over t o Operat ions w i t h several t e s t except ions l e f t outstand- ing. the Subsystem. Operator t r a i n i n g on the Subsystem i s being pursued.
Most o f the t e s t except ions are minor and do no t prevent opera t ion of
48
The FCS s tores data on a magnetic tape f o r h i s t o r i c a l and f u r t h e r s tudy
purposes. Ths program i s about 20% complete.
A computer program i s be ing w r i t t e n to decode t h a t s tored data. Q
F a i l u r e Locat ion -- A i r and hydrocarbons cont inued t o appear i n mass
spec t romet r ic analyses o f gas obta ined us ing the Gas Tag Sampling Trap (GTST) b u t no t i n the small, U-tube l a b o r a t o r y t rap. Valves on a t l e a s t two
of t he GTST assemblies were determined to be l e a k i n g i n both d i r e c t i o n s and may be the cause o f the problems.
i n order t o make cor rec t ions .
FFTF Operations i s examining the valves
A l i gh te r -we igh t , somewhat smal ler t r a p design was proposed t h a t could
be used throughout most of the p l a n t ' s l i f e .
were designed and f a b r i c a t e d f o r use under cond i t i ons o f the f a i l u r e of two h i g h rod power pins, an u n l i k e l y event du r ing most of the p l a n t ' s l i f e . The
proposed des ign recommends us ing 80 g o f charcoal ins tead o f 175 g t o reduce the impact o f 23Ne and '41Ar on the dose ra tes , w h i l e no t compromising
the Xe and K r t rapp ing c a p a b i l i t y . a c t i v i t y l e v e l s i n the cover gas under f a i l e d f u e l cond i t i ons makes p o s s i b l e
the use o f aluminum i n p lace of s tee l as s h i e l d m a t e r i a l w h i l e s t i l l r e t a i n i n g the 500 mR/h dose r a t e l i m i t .
Smaller, l i g h t e r and l e s s sub jec t t o i m p u r i t y d i f f i c u l t i e s .
The present GTST assemblies
That reduc t i on combined w i t h expected
The proposed des ign would be
The fo rma t ion of a F a i l e d Element Locat ion Team, a small group t h a t would n o t i f y P l a n t opera t ions o f the l o c a t i o n o f a f a i l e d f u e l o r absorber
element, was begun. a n a l y t i c a l da ta and core in format ion, the l o c a t i o n o f the f a i l e d element by
assembly number, and f o r recommending t o P lan t Operat ions the course of a c t i o n to be taken.
The team would be respons ib le f o r de termin ing f rom GTST
n
49
3 .
F.
1.
F u t ure W or k
Provide technical support as needed.
Provi de Fai 1 ure Character i z a t i on Subsys tem t ra i ni ng . FUEL FAILURE MONITORING - EBR-I1 PROOFTEST F. E. Holt and D. V. Archer
Objective
This task provides design verification and performance evaluations of Fuel Failure Monitoring (FFM) components on an operating f a s t reactor.
2. Accompl i shmen ts
Absorber/Collimator ( A / C ) Test -- The responses of the two A/C devices were tested dur ing this quarter to determine their effectiveness. The Detector and A/C device No. 1 responded as expected, equivalent t o labora- tory tes t s , and resulted i n gama ray intensi ty reduction factors that increased the range of count ra tes accommodated. The Detector and A/C device No. 2 data yielded unexpected, and as yet unexplained, resul ts f o r Position 3 b u t agreed w i t h laboratory tes t s for Positions 2 and 4.
Each A / C device was manually set over a four-day period to count in C o u n t i n g times were three of i t s four positions for a fixed period of time.
se t a t 700, 2000, 7000 and 9000 seconds. The counting time chosen was dependent on the amount of intensi ty reduction expected and the predicted cover gas act ivi ty .
There is generally excellent agreement between the Proof t es t and GLASS data as evidenced by the percent, 1 CY precisions. various energies ranged from 7 x 10-3/s to lOOO/s.
Counting rates for the
50
A t the end o f the test period, the several outputs from each detector and A/C posit ions were compared against the EBR-I1 p lan t ' s corresponding GLASS monitoring system o u t p u t s . c/s per d/s-ml values in the Tables, one obtains the intensi ty reduction factors versus A/C position. for 133Xe 81 keV gama ray when counting in Position 3 versus Position 1 i s 0.0714/0.00218 = 32.7 - + 1.9.
Tables 8 and 9 l i s t the resu l t s . From the
For example from Table 8 the reduction factor
Table 10 l i s t s the calculated factors and the laboratory measured ones from the l a s t quarterly report. (3 1
Conversion of Computer Program -- The computer program used to decode the Prooftest ' s data stored on magnetic tape i s being converted from CYBER t o VAX processing. Conversion of the applicable programs i s almost complete.
The CYBER computer i s being phased ou t of service,
Gamma Ray Subtract (GRS) Module Modification -- The GRS prototype module was modified to add a t h i r d set of countrate multipliers. set o f mult ipl iers will be used to normalize A/C Position 4 countrates to Postiion 1 countrates. The added f l e x i b i l i t y is needed whenever the Posi- t ion 4 configuration is not a simple combination of Positions 2 and 3 . s i tua t ion occurs w i t h the lead plug used in A/C Position 4, Detector No. 2 and w i t h the use of "compound" absorber/col limators in d i f fe ren t tungsten col 1 imators .
The added
That
The modification was accomplished by an outside vendor and tested i n the laboratory. The outputs obtained were as expected. The prototype control panel and microprocessor with the new program were sent t o EBR-I1 f o r further testing. panels were wired s l igh t ly d i f fe ren t ly as the t e s t s could not a l l be completed. and finish the requested tests.
Unfortunately, the prototype and instal led control
Personnel a t EBR-I1 will modify the Prooftest ' s control panel
3. Future Work
Determine cause of A/C No. 2, Position 3 reduction factor discrepancy. Complete Prooftest computer program conversion. Test modified GRS module a t EBR- 11.
51
TABLE 8
DETECTOR l/GLASS 1 RATIOS VS A/C POSITION
Counting A/C Time ( s r poS 133Xe a t 81 keV 135Xe a t 250 keV 135Xe a t 608 keV
c/s Der c/s per c /s Der . I
c/nCi -ml d/s-ml c/nCi -ml d/s-ml c/nCi -ml d/s-ml - - -
700 1 X7 = 1850 7.14 E-2 x9 = 584 2.26 E-2 X7 = 2.70 1.04 E-4 + 1.1% - + 1.3% - + 8.7% -
- - - 2000 3 Xi4 = 150 2.08 E-3 X i 3 = 131 1.77 E-3 Xi3 = 3.89 5.27 E-5
+ 5.7% - + 2.9% - + 15% -
- - - 7000 4 X4 = 14.2 5.48 E-5 X4 = 24.6 9.50 E-5 X4 = 1.32 5.10 E-6
+ 8.2% - + 43% - + 1.3% -
- - - 9000 4 X 1 1 = 19.7 5.92 E-5 X10 = 31.7 9.52 E-5 X12 = 1.67 5.02 E-6
+ 8.9% - + 24% - + 15% -
TABLE 9
DETECTOR 2/GLASS 2 RATIOS VS A/C POSITION
A /C - Pos 133Xe a t 81 keV 135Xe a t 250 keV 135Xe a t 608 keV
c/s per c/s per c/s per c/nCi -ml d/s-ml c/nCi -ml d/s-ml c/nCi-ml d/s-ml
700 If Xi0 = 22144 0.855 Xi0 = 14305 0.552 X i 0 = 97.0 0.00375 - - -
- + 1.3% - + 0.8% - + 1.1%
- - - Xi4 = 1108 0.0150 Xi4 = 807 0.0109 X i4 = 11.1 0.00015 2000 2
- + 3.4% - + 2.2% - + 12%
- - - 700 3 x6 = 489 0.0189 x6 = 991 0.0383 x6 = 49.6 0.00192
- + 4.6% - + 1.0% - + 3.2%
- - - '4 = 4921 0.0190 x4 = 9901 0.0382 X4 = 491 0.00189 7000 3
+ 2.6% - + 1.0% - + 0.9% -
- - 9000 4 - - Xg = 60.2 0.00018 X i 1 = 248 0.00074
- + 5.6% - + 6.3% ~ ~~
*Data from 5/3/80 (Position 1 not used during this 7/29 t o 8/4/80 A/C t e s t ) .
A /C
TABLE 10
GAMMA RAY REDUCTION FACTOR COMPARISONS VS A/C POSITION AND DETECTOR
Detector No. 1 Detector No. 2 A I C Lab A I C Lab . ., -
Test - Pos N i Test Test Test - 2 133Xe a t 8 1 keV
135Xe a t 250 keV 135Xe a t 608 keV
57 - + 2 55 51 - + 1 45
25 - + 3 22
3 1 3 3 ~ e 33 - + 2 25 45 - + 2 1070*
135 Xe 12.7 - + 0.4 10 1.44 - + 0.3 270*
1 3 5 ~ e 2.0 - + 0.3 2 2.0 - + 0.1 23*
1206 + 180 1070 - - 4 133~e - 135 ~e 237 - + 21 27 0 3050 - + 170 3300
1 3 5 ~ e 21 - + 5 23 5.0 - + 0.3 5.5
*Cannot e x p l a i n t h i s discrepancy. EBR- I 1 personnel determined t h a t t he c o r r e c t A/C c o n f i g u r a t i o n i s i n t h i s p o s i t i o n .
54
I1 I . REFERENCES
1. J. M. Atwood, e t al. , Sodium Technology Progress Report, October- December 1979, HEDL-TME 79-27, Hanford Engineer ing Development Laboratory , Richland, WA, A p r i l 1980.
2. J. M. Atwood, e t al., Sodium Technology Progress Report, January- March 1980, HEDL-TME 80-30, Hanford Engineering Development Laboratory, Richland, WA, June 1980.
3. J. M. Atwood, e t al., Sodium Technology Progress Report, A p r i l - June 1980, HEDL-TME 80-31, Hanford Engineering Development Laboratory, Richland, WA, September 1980.
4. J. M. Atwood, e t al., Sodium Engineer ing and Technology Technical Progress Report, January, February, March 1978, HEDL-TME 78-20, Hanford Engineer ing Development Laboratory, R i c h l and, WA, August 1978.
5. J. M. Atwood, e t al., Sodium Technology Progress Report, July-September - 1979, HEDL-TME 79-26, Hanford Engineer ing Development Laboratory, Rich1 and, WA, January 1980.
6. W. L. Kuhn, A c t i v a t e d Corrosion Product Rad ia t i on Levels i n t h e FFTF Heat Transpor t System C e l l s and Closed Loop System Modules, HEDL-TME 16-10 , Hanford Enqineer inq Development Laboratory, - - . Richland, WA, September 1977.
7. R. P. Anantatmula, J. M. Lut ton, and M. 8. H a l l , "Decontamination o f Breeder Reactor Components," Sodium Technology Progress Report, Ju l y - Se tember 1979, HEDL-ME 79-26, Hanford Engineer ing Development re----- aboratory, Richland, WA, January 1980.
8. R. P. Anantatmula. et al,. "Decontamination o f Breeder Reactor Components,'' Sod i im Technology Progress Report, January-March 1980, HEDL-TME 80-30, Hanford Engineer ing Development Laboratory, Richland, WA, September 1980.
9. R. P. Anantatmula, e t al., "Decontamination o f Breeder Reactor Components,'I Sodium Technology Progress Report, Ap r i l - June 1980, HEDL-TME 80-31. WA, September 1980.
Hanford Engineer ing Development Laboratory, Richland,
10. C. Bagnal l and S. A. Shiels, " E q u i l i b r i u m S t ruc tu res o f Type 304 and Type 316 S t a i n l e s s Steel i n t h e Temperature Range 8OOOF - 15OO0F," <meta l l og raph ic review, presented a t t h e Ninth-Annual Conference of t h e I n t e r n a t i o n a l Me ta l l og raph ic Society, Seat t le , WA, J u l y 1976.
55
REFERENCES (Cont I d )
11.
12.
13.
W. H. Yunker, " S i l i c o n Mass Trans fer i n Sodium Loops and the Resu l t i ng Thermal /Hydrau 1 I c Ef fec ts , I' i n Proceedings of t h e Second I n t e r n a t i o n a l Conference on L i q u i d Metal Technology i n Energy Production, R ich 1 and, WA 9 A p r i l 1980.
W. W. Humphreys and J. R. Welty, "Natura l Convection w i t h Mercury i n a Un i fo rmly Heated Channel Dur ing Unstable Laminar and T r a n s i t i o n Flow," Journal o f AIChE, pp. 268-274, March 21, 1975.
J. M. Atwood, Sodium Technology Progress Report, October-December 1978, HEDL-ME 78-93, Hanford Engineer ing Development Laboratory, Rich land, WA, March 1979.
56
HEDL-TME 80-32 UC-79a
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