Associazione EURATOM ENEA sulla FUSIONE KOM Meeting of the contracts TW5- TSW-001 and -002 Garching. January 18 th, 2006 Kick Off Meeting of the contracts

Associazione EURATOM ENEA sulla FUSIONEKOM Meeting of the contracts TW5- TSW-001 and -002Garching. January 18th, 2006

Kick Off Meeting of the contracts

TW5-TSW-001 and -002

ENEA part of the Art.5.1.a. task, and reminder of former results and reports

L.Di PaceENEA CR Frascati

Garching, January 18th, 2006

2Associazione EURATOM ENEA sulla FUSIONE

KOM Meeting of the contracts TW5- TSW-001 and -002Garching. January 18th, 2006

Outline

•Aim of the task;

•Deliverable 1;

•Deliverable 6;

•Schedule.



Aim of the taskStudy on Recycling of Fusion Activated Materials;

As shown by the PPCS study, all or most of the active materials arising from the operation and decommissioning would be suitable for recycling, after up to 100 years of intermediate storage. Radiological criteria, mostly based on dose rates, have been commonly used to determine if materials would be candidates for recycling. However it is not clear conditions at which recycling, for example in fabrication of components for new fusion power plants, would actually be feasible. Open questions include the availability of suitable processes, the ability to process active material and fabricate new components using RH techniques, and the economic viability of such processes.



Deliverable 1

• This deliverable will define components and materials involved and determine volumes & masses for PPCS Model AB considering the main boundary conditions.

• Data from the report UKAEA/TW4-TRP-002 Deliverable 2e Jan 2005 [UKAEA/TW4-TRP-002] and related neutron transport and activation calculations available on CD.



Deliverable 1



Deliverable 1CELL VOLUME (m3)

Angle layer 1 layer 2 layer 3 layer 4 layer 5 layer 6 layer 7 layer 8 layer 9 layer 10 layer 1111 6,43E+02 1,60E+02 4,00E+01 4,83E+01 2,78E+01 1,98E+01 1,85E+01 1,73E+01 1,60E+01 1,99E+00 1,57E-0133 7,61E+02 2,08E+02 5,44E+01 6,81E+01 4,07E+01 2,97E+01 2,86E+01 2,75E+01 2,64E+01 3,32E+00 2,00E-0155 9,81E+02 2,70E+02 7,11E+01 8,91E+01 5,35E+01 3,91E+01 3,77E+01 3,63E+01 3,49E+01 4,39E+00 3,75E-0177 1,17E+03 3,12E+02 8,12E+01 1,01E+02 6,00E+01 4,37E+01 4,20E+01 4,02E+01 3,83E+01 4,85E+00 4,11E-0199 1,17E+03 3,12E+02 8,12E+01 1,01E+02 6,00E+01 4,37E+01 4,20E+01 4,02E+01 3,83E+01 4,85E+00 4,11E-01

121 9,81E+02 2,70E+02 7,11E+01 8,91E+01 5,35E+01 3,91E+01 3,77E+01 3,63E+01 3,49E+01 4,39E+00 3,75E-01143 7,61E+02 2,08E+02 5,44E+01 6,81E+01 4,07E+01 2,97E+01 2,86E+01 2,75E+01 2,64E+01 3,32E+00 2,00E-01165 6,43E+02 1,60E+02 4,00E+01 4,83E+01 2,78E+01 1,98E+01 1,85E+01 1,73E+01 1,60E+01 1,99E+00 1,57E-01187 3,12E+02 7,89E+01 2,33E+01 2,94E+01 1,90E+01 9,86E+00 9,20E+00 8,52E+00 8,44E+00 1,25E+00 9,70E-02209 1,14E+02 3,52E+01 1,47E+01 2,15E+01 1,77E+01 6,80E+00 6,72E+00 6,62E+00 8,12E+00 1,61E+00 1,32E-01231 9,27E+01 3,46E+01 1,53E+01 2,35E+01 2,05E+01 8,19E+00 8,24E+00 8,31E+00 1,05E+01 2,12E+00 1,68E-01253 9,20E+01 3,63E+01 1,64E+01 2,55E+01 2,25E+01 9,07E+00 9,19E+00 9,34E+00 1,18E+01 2,40E+00 1,68E-01275 9,20E+01 3,63E+01 1,64E+01 2,55E+01 2,25E+01 9,07E+00 9,19E+00 9,34E+00 1,18E+01 2,40E+00 1,68E-01297 9,27E+01 3,46E+01 1,53E+01 2,35E+01 2,05E+01 8,18E+00 8,25E+00 8,31E+00 1,05E+01 2,11E+00 1,68E-01319 1,14E+02 3,52E+01 1,47E+01 2,15E+01 1,77E+01 6,81E+00 6,71E+00 6,62E+00 8,12E+00 1,61E+00 1,32E-01341 3,12E+02 7,89E+01 2,33E+01 2,94E+01 1,90E+01 9,86E+00 9,20E+00 8,52E+00 8,43E+00 1,25E+00 9,70E-02

CELL MASS (kg)Angle layer 1 layer 2 layer 3 layer 4 layer 5 layer 6 layer 7 layer 8 layer 9 layer 10 layer 11

11 3,46E+06 8,14E+05 4,44E+05 2,28E+05 1,31E+05 9,34E+04 8,75E+04 8,16E+04 7,54E+04 3,82E+04 3,02E+0333 4,09E+06 1,06E+06 6,05E+05 3,22E+05 1,92E+05 1,41E+05 1,35E+05 1,30E+05 1,25E+05 6,40E+04 3,85E+0355 5,28E+06 1,37E+06 7,90E+05 3,51E+05 2,11E+05 2,96E+05 2,86E+05 2,75E+05 2,64E+05 2,42E+04 7,22E+0377 6,29E+06 1,59E+06 9,01E+05 3,99E+05 2,37E+05 3,31E+05 3,18E+05 3,05E+05 2,90E+05 2,68E+04 7,91E+0399 6,29E+06 1,59E+06 9,01E+05 3,99E+05 2,37E+05 3,31E+05 3,18E+05 3,05E+05 2,90E+05 2,68E+04 7,91E+03

121 5,28E+06 1,37E+06 7,90E+05 3,51E+05 2,11E+05 2,96E+05 2,86E+05 2,75E+05 2,64E+05 2,42E+04 7,22E+03143 4,09E+06 1,06E+06 6,05E+05 2,68E+05 1,60E+05 2,25E+05 2,17E+05 2,08E+05 2,00E+05 1,83E+04 3,85E+03165 3,46E+06 8,14E+05 4,44E+05 1,90E+05 1,10E+05 1,50E+05 1,40E+05 1,31E+05 1,21E+05 1,10E+04 3,02E+03187 1,68E+06 4,02E+05 2,58E+05 1,16E+05 7,51E+04 7,47E+04 6,97E+04 6,45E+04 6,39E+04 6,86E+03 1,87E+03209 6,14E+05 1,79E+05 1,63E+05 8,47E+04 6,97E+04 5,15E+04 5,09E+04 5,01E+04 6,15E+04 8,85E+03 2,54E+03231 4,98E+05 1,76E+05 1,70E+05 9,28E+04 8,06E+04 6,20E+04 6,24E+04 6,29E+04 7,93E+04 1,17E+04 3,23E+03253 4,95E+05 1,85E+05 1,82E+05 1,01E+05 8,86E+04 6,87E+04 6,96E+04 7,07E+04 8,93E+04 1,32E+04 3,24E+03275 4,95E+05 1,85E+05 1,82E+05 1,01E+05 8,86E+04 6,87E+04 6,96E+04 7,07E+04 8,93E+04 1,32E+04 3,24E+03297 4,98E+05 1,76E+05 1,70E+05 9,28E+04 8,06E+04 6,19E+04 6,25E+04 6,29E+04 7,93E+04 1,16E+04 3,23E+03319 6,14E+05 1,79E+05 1,63E+05 1,02E+05 8,35E+04 3,22E+04 3,17E+04 3,12E+04 3,84E+04 3,09E+04 2,54E+03341 1,68E+06 4,02E+05 2,58E+05 1,39E+05 8,99E+04 4,66E+04 4,35E+04 4,03E+04 3,98E+04 2,40E+04 1,87E+03

SUMMARY

volume (m3) mass (kg) material composition2,83E+00 5,45E+04 W3,57E+01 1,97E+05 steel + He1,02E+03 7,74E+06 LiPb + steel + He4,18E+02 1,65E+06 steel + He6,46E+02 2,55E+06 steel + He6,33E+02 7,02E+06 WC + steel + water2,27E+03 1,16E+07 steel + boron + water8,33E+03 4,48E+07 ITER coil mixture5,21E+02 2,46E+06 steel + He8,75E+00 1,68E+05 W1,39E+04 7,82E+07

componentblanket armourblanket FWblanket breederblanket manifoldHT shieldLT shieldvacuum vesselTF coilsdivertor structure

totaldivertor tiles



Deliverable 6

• Define interim clearance levels for the missing radionuclides not included the IAEA Safety Guide (SG) No. RS-G-1.7 [IAEA RS-G-1.7].

• The recent IAEA SG No. RS-G-1.7 has defined “Application of the Concepts of Exclusion, Exemption and Clearance”, providing specific activity levels for exemption and clearance, dividing radionuclides of natural origin from the artificial ones.

• The list of artificial radionuclides for which clearance levels are given includes about 260 nuclides, while the previous IAEA TECDOC-855 was able to provide (directly or indirectly) clearance levels for ~ 1650 nuclides.

• The proposal is to provide interim clearance levels for missing radionuclides based on the application of the Radio Toxicity Index to derive clearance level (see reference [ICEM03]).



Deliverable 6• Preliminary comparison done by ENEA

between CLs IAEA TECDOC-855, Safety Guide (SG) No. RS-G-1.7 and EC RP 122

• 1 [clearance comparison new] using a spread-sheet;

• 2 [ENEA TR 135.doc] by dedicated ANITA calculations.



Deliverable 6• Preliminary comparison between CLs of IAEA TECDOC-855 and

SG No. RS-G-1.7 from paper “The Feasibility of Recycling and Clearance of Active Materials from Fusion Power Plants” by M. Zucchetti, L.A. El-Guebaly, R.A. Forrest, T.D. Marshall, N.P. Taylor, K. Tobita [ICFRM-12]

Clearance index of material from part of the VV of PPCS Plant Model C



Deliverable 6Definition of a Toxicity Index [ICEM03]

• U has been the basis of the fission power industry;• It is found in nature in concentrations from 0.1 to 1%;• As U is radioactive and quite common in the earth’s crust

as ore (U3O8), it might be used as a benchmark for comparing potential fusion radioactive waste.

• For this comparison U ore with 1% is assumed (˜100% U-238). U-238 specific activity= 1.24x107 Bq/kg. U ore (1% of U-238) the specific activity is 1.24x105 Bq/kg.

• The ingestion dose conversion factor of U-238, relevant to the public, is 4.50x10-8 Sv/Bq. Therefore, the radio-toxicity of uranium ore (at 1%), is 5.6x10-3 Sv/kg. U-238 radiotoxicity is 100 times larger: 5.48x10-1 Sv/kg.

• We define the Toxicity Index (TI) as the radio-toxicity of any substance relative to that natural uranium ore.



• Toxicity Index for PWR spent fuel (actinides)

Typical PWR spent fuel contains ~ 9 g of actinides (mostly Pu-239) and about 35 g of FPs per kg of fuel.

- Pu-239 should represent the greatest risk to future generations. - Pu-239 has been assumed to account for the entire mass of actinides.

This is equivalent to (9/239) 0.0376 moles or 2.27x1022 atoms. t1/2 of Pu-239 = 24,100 years, hence, the radio-activity in the 1-kg sample is 2.07x1010 Bq.

- The ingestion dose conversion factor for Pu-239 is 2.50x10-7 Sv/Bq. The PWR spent fuel radio-toxicity is 5.17x103 Sv/kg – almost 106 times the uranium ore TI.

- TI for PWR spent fuel (due to actinides) decreases with time, as Pu-239 has a short half-life, relative to that (4.5 billion years) of U-238 At ~ 500,000 y it becomes the same radio-toxicity of the natural U ore.

Deliverable 6



• Toxicity Index for spent fuel (fission products)

Tc-99, I-129 and Sn-126 have the largest radiotoxicity. Their TI is at least one order of magnitude lower than U-238 and four orders of magnitude lower than Pu-239. Cs-137 and Sr-90 not taken into account due to their short t1/2.

Deliverable 6

Radio Toxicity Index Used PWR Fuel

1E-06

1E-05

1E-04

1E-03

1E-02

1E-01

1E+00

1E+01

1E+02

1E+03

1E+04

1E+05

1E+06

1E-01 1E+00 1E+01 1E+02 1E+03 1E+04 1E+05 1E+06

Time [y]

RT

I

Tc-99

I-129

Sn-126

Se-79

Zr-93

Cs-135

Ca-41

Pd-107

U-238

Pu-239



Sanity check of IAEA TECDOC-855 and EC-RP 122 CLs of the RTI by spreadsheet using RTI < 0.001 as preliminary clearance level has started.

Deliverable 6

According to table I of TECDOC 855 and using 5,60E-03 Sv/kg as radiotoxicity for U oreRTI < 0,001Ingestion

Nuclide Half Life, a Lc,Bq/g Sv/Bq for workers

Radiotoxicity (Sv/kg)

RTI Dose Conversion factors for Ingestion Dose from IAEA Safety Series No. 115 and from COUNCIL DIRECTIVE 96/29/EURATOM

H-3 12,35 3000,0 1,80E-11 5,40E-05 0,010 RTI adequateS-35 2,39E-01 3000,0 7,70E-10 2,31E-03 0,413 RTI adequate

Ca-45 4,46E-01 3000,0 7,60E-10 2,28E-03 0,407 RTI adequateNi-63 96 3000,0 1,50E-10 4,50E-04 0,080 RTI adequate

Pm-147 2,62E+00 3000,0 2,60E-10 7,80E-04 0,139 RTI adequateC-14 5,73E+03 300,0 5,80E-10 1,74E-04 0,031 RTI adequateP-32 3,92E-02 300,0 2,40E-09 7,20E-04 0,129 RTI adequateCl-36 3,01E+05 300,0 9,30E-10 2,79E-04 0,050 RTI adequateFe-55 2,70E+00 300,0 3,30E-10 9,90E-05 0,018 RTI adequateSr-89 1,38E-01 300,0 2,60E-09 7,80E-04 0,139 RTI adequateY-90 7,31E-03 300,0 2,70E-09 8,10E-04 0,145 RTI adequateTc-99 2,13E+05 300,0 7,80E-10 2,34E-04 0,042 RTI adequate

Cd-109 1,27E+00 300,0 2,00E-09 6,00E-04 0,107 RTI adequateCr-51 7,58E-02 30,0 3,80E-11 1,14E-06 2,0E-04 RTI not adequateCo-57 7,42E-01 30,0 2,10E-10 6,30E-06 1,1E-03 RTI adequate

Tc99-m 6,87E-04 30,0 2,20E-11 6,60E-07 1,2E-04 RTI not adequateI-123 1,51E-03 30,0 2,10E-10 6,30E-06 1,1E-03 RTI adequateI-125 1,65E-01 30,0 1,50E-08 4,50E-04 0,080 RTI adequateI-129 1,57E+07 30,0 1,10E-07 3,30E-03 0,590 RTI adequate

Ce-144 7,78E-01 30,0 5,20E-09 1,56E-04 0,028 RTI adequateTl-201 8,32E-03 30,0 9,50E-11 2,85E-06 0,001 RTI not adequatePu-241 1,44E+01 30,0 4,70E-09 1,41E-04 0,025 RTI adequate



Schedule

Deliver. Nov-Dec Jan-Fev Mar-Apr May-Jun July-Aug Sep-Oct Due Date

D1.1. 28/02/06 31/03/06

D1.2. 31/05/06

D1.3. 30/06/06

D1.4. 31/10/06

D1.5. 31/10/06

D4. 31/10/06

D5. 31/10/06

Meetings X X X

Activities From To 1. Report on definition of components and materials involved in recycling

3 months

from the sign of the contract

2. Report on the categories of wastes (based on international standards) and on results of the cycle analysis

9 months

from the sign of the contract

From note by V. Massaut dated October 6th 2005

extension

From ENEA subtask summary page issued on Nov. 10 th

Documents

Associazione EURATOM ENEA sulla FUSIONE KOM Meeting of the contracts TW5- TSW-001 and -002 Garching. January 18 th, 2006 Kick Off Meeting of the contracts