associazione euratom enea sulla fusione final meeting of the tasks tw5-tsw-001, 001b, -002 23-24...

Associazione EURATOM ENEA sulla FUSIONEFinal Meeting of the Tasks TW5-TSW-001, 001B, -00223-24 October 2006, UKAEA, Culham, UK

Final meeting tasks TW5-TSW-001, -001B, -002

D1 & D6

L. Di PaceENEA CR Frascati

23-24 October 2006, UKAEA, Culham, UK

2Associazione EURATOM ENEA sulla FUSIONE

Final Meeting of the Tasks TW5-TSW-001, 001B, -00223-24 October 2006, UKAEA, Culham, UK

Outline

• Aim of the task;• Work done for TW5-TSW-001 D1;• Work done for TW5-TSW-001-D6;• 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 [TW4-TRP-002D2e_rev1]

and related neutron transport and activation calculations available on CD.



Work done for D1

Input data



Work done for D1CELL 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

Input dataExcel file from R.

Pampin (UKAEA) clearance levels based on IAEA TECDOC-855 (1996)



Work done for D1

• Analysis focused on all component materials.• Basic criteria used to check

recycling/clearance feasibility:– Clearance index (for clearance) [IAEA-TECDOC-

855];– Dose rate < 2 mSv/h (for recycling);– Decay heat < 1 W/m3 (for recycling);– Specific Activity <1 KBq/g (for recycling)

operative value suggested in SCK•CEN report [R-4056 276/05-01 February 2005] (“During the several discussions with experts of the melting facilities, an activity level of 1000 Bq/g should be feasible to handle without remote control, higher values demand remote handling”).



Work done for D1

• TF coils and VV design similar to ITER;

ITER Magnet System ITER Vacuum Vessel



Work done for D1• In-vessel modules design for PPCS Model AB



Work done for D1• In-vessel modules design for PPCS Model AB

FW/SW

Cover

Stiffening Grid

He outlet He inlet

Pb-Li inlet Pb-Li outlet

BUsPb-Lidistribution box

BPs



Work done for D1TF Coils

Clearance Index < 1

At shut down 64% of mass is clearable, it increases up to 86% after t 50 y.

Mass in kg

limit < 1Angle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341

Cells C 1 C15 C29 C43 C57 C71 C85 C99 C113 C127 C141 C155 C169 C183 C197 C211zero 3,75E-01 1,46E-01 1,46E-01 1,46E-01 1,46E-01 1,46E-01 1,46E-01 1,46E-01 1,49E+02 1,79E+03 2,37E+03 3,64E+03 3,83E+03 2,33E+03 6,90E+02 4,21E+01

40 days 4,48E-02 2,41E-02 2,41E-02 2,41E-02 2,41E-02 2,41E-02 2,41E-02 2,41E-02 2,46E+01 2,90E+02 4,00E+02 5,99E+02 6,31E+02 3,98E+02 1,13E+02 6,28E+0010 years 1,14E-02 6,18E-03 6,18E-03 6,18E-03 6,18E-03 6,18E-03 6,18E-03 6,18E-03 4,53E+00 5,39E+01 7,05E+01 1,09E+02 1,12E+02 6,90E+01 2,03E+01 1,24E+0050 years 4,07E-04 2,51E-04 2,51E-04 2,51E-04 2,51E-04 2,51E-04 2,51E-04 2,51E-04 1,50E-01 1,86E+00 2,36E+00 3,65E+00 3,81E+00 2,28E+00 6,90E-01 4,22E-0277 years 3,51E-04 2,21E-04 2,21E-04 2,21E-04 2,21E-04 2,21E-04 2,21E-04 2,21E-04 1,27E-01 1,59E+00 2,01E+00 3,11E+00 3,25E+00 1,93E+00 5,88E-01 3,59E-02

100 years 3,49E-04 2,20E-04 2,20E-04 2,20E-04 2,20E-04 2,20E-04 2,20E-04 2,20E-04 1,26E-01 1,58E+00 1,99E+00 3,08E+00 3,22E+00 1,92E+00 5,84E-01 3,57E-02

Clearance Index (-)TF coils

at shut down clerable mass 1,15E+07 64%not clearable mass 6,57E+06 36%

1,80E+07at t = 10 y clerable mass 1,15E+07 64%

not clearable mass 6,57E+06 36%1,80E+07

at t = 50 y clerable mass 1,54E+07 86%not clearable mass 2,60E+06 14%

1,80E+07




Decay heat < 1 W/m3limit < 1 W/m3

Angle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341Cells C 1 C15 C29 C43 C57 C71 C85 C99 C113 C127 C141 C155 C169 C183 C197 C211zero 5,59E-07 2,13E-07 2,13E-07 2,13E-07 2,13E-07 2,13E-07 2,13E-07 2,13E-07 2,14E-04 2,56E-03 3,36E-03 5,19E-03 5,43E-03 3,30E-03 9,84E-04 6,08E-05

40 days 3,16E-08 1,68E-08 1,68E-08 1,68E-08 1,68E-08 1,68E-08 1,68E-08 1,68E-08 1,63E-05 1,92E-04 2,62E-04 3,95E-04 4,13E-04 2,59E-04 7,42E-05 4,20E-0610 years 7,69E-09 4,15E-09 4,15E-09 4,15E-09 4,15E-09 4,15E-09 4,15E-09 4,15E-09 3,07E-06 3,66E-05 4,79E-05 7,37E-05 7,58E-05 4,68E-05 1,38E-05 8,44E-0750 years 2,29E-10 1,31E-10 1,31E-10 1,31E-10 1,31E-10 1,31E-10 1,31E-10 1,31E-10 9,20E-08 1,12E-06 1,44E-06 2,23E-06 2,32E-06 1,40E-06 4,18E-07 2,56E-08

100 years 1,79E-10 1,05E-10 1,05E-10 1,05E-10 1,05E-10 1,05E-10 1,05E-10 1,05E-10 6,78E-08 8,33E-07 1,06E-06 1,65E-06 1,73E-06 1,03E-06 3,11E-07 1,90E-08

Decay Heat (W/m3)TF coils

limit < 2 mSv/hAngle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341

Cells C 1 C15 C29 C43 C57 C71 C85 C99 C113 C127 C141 C155 C169 C183 C197 C211zero 8,36E-05 3,17E-05 3,17E-05 3,17E-05 3,17E-05 3,17E-05 3,17E-05 3,17E-05 3,37E-02 4,02E-01 5,35E-01 8,18E-01 8,62E-01 5,26E-01 1,55E-01 9,48E-03

40 days 9,60E-06 5,13E-06 5,13E-06 5,13E-06 5,13E-06 5,13E-06 5,13E-06 5,13E-06 4,84E-03 5,70E-02 7,75E-02 1,17E-01 1,22E-01 7,65E-02 2,21E-02 1,25E-0310 years 2,41E-06 1,30E-06 1,30E-06 1,30E-06 1,30E-06 1,30E-06 1,30E-06 1,30E-06 9,54E-04 1,14E-02 1,49E-02 2,29E-02 2,35E-02 1,46E-02 4,29E-03 2,62E-0450 years 5,28E-08 3,22E-08 3,22E-08 3,22E-08 3,22E-08 3,22E-08 3,22E-08 3,22E-08 1,95E-05 2,42E-04 3,07E-04 4,75E-04 4,94E-04 2,97E-04 8,97E-05 5,48E-06

100 years 4,05E-08 2,56E-08 2,56E-08 2,56E-08 2,56E-08 2,56E-08 2,56E-08 2,56E-08 1,46E-05 1,83E-04 2,31E-04 3,58E-04 3,74E-04 2,23E-04 6,78E-05 4,14E-06

Contact dose rate (mSv/h)TF coils

Mass in kg

Mass in kg

at shut downMass below limit 1 W/m3 1,80E+07 100%

Mass above limit 0,00E+00 0%1,80E+07

Contact Dose rate < 2 mSv/h

at shut downMass below limit 2 mSv/h 1,80E+07 100%





Specific activity < 1 KBq/g

After 40 d all TF coil is < 1000 Bq/g, even though the CL is not reached for 14% of the TF coil mass at 100 y.

Clearable mass does not change up to t > 10 and < 50 y. At SD, 64% of the TF coil is already clearable.

Up to 86% of the TF coil mass is clearable, the remaining 14% is recyclable.

Possible limitation from the segmentation of the different strand materials.

limit < 1000 Bq/gAngle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341

Cells C 1 C15 C29 C43 C57 C71 C85 C99 C113 C127 C141 C155 C169 C183 C197 C211zero 1,12E+00 4,65E-01 4,65E-01 4,65E-01 4,65E-01 4,65E-01 4,65E-01 4,65E-01 3,92E+02 4,76E+03 6,15E+03 9,64E+03 1,00E+04 5,99E+03 1,82E+03 1,14E+02

40 days 6,03E-02 2,27E-02 2,27E-02 2,27E-02 2,27E-02 2,27E-02 2,27E-02 2,27E-02 3,41E+01 4,10E+02 5,67E+02 8,63E+02 9,18E+02 5,83E+02 1,62E+02 9,66E+0010 years 8,89E-03 3,87E-03 3,87E-03 3,87E-03 3,87E-03 3,87E-03 3,87E-03 3,87E-03 4,84E+00 5,68E+01 7,65E+01 1,18E+02 1,24E+02 7,67E+01 2,17E+01 1,37E+0050 years 2,23E-03 6,97E-04 6,97E-04 6,97E-04 6,97E-04 6,97E-04 6,97E-04 6,97E-04 1,19E+00 1,37E+01 1,85E+01 2,86E+01 3,00E+01 1,82E+01 5,28E+00 3,25E-01

100 years 1,54E-03 4,36E-04 4,36E-04 4,36E-04 4,36E-04 4,36E-04 4,36E-04 4,36E-04 7,36E-01 8,52E+00 1,16E+01 1,78E+01 1,87E+01 1,13E+01 3,32E+00 2,01E-01

Specific Activity (Bq/g)TF coils

Mass in kg

Remarks on TF Coils

at shut downMass below limit 1 W/m3 1,48E+07 82%


at t = 40 daysMass below limit 1 W/m3 1,80E+07 100%




Work done for D1BL First Wall

Clearance Index < 1

At t = 100,000 y no clearable mass

Mass = 1.97 E+05 kg

limit < 1Angle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341

Cells C13 C27 C41 C55 C69 C83 C97 C111 C125 C139 C153 C167 C181 C195 C209 C223zero

10 years50 years

100 years1000 years

10000 years

BL FW

ALWAYS > 1Clearance Index (-)



Work done for D1Decay heat < 1 W/m3

Contact Dose rate < 2 mSv/h

BL First Wall

Mass in kg

Mass in kg

limit < 1 W/m3 or 10 W/m3Angle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341

Cells C13 C27 C41 C55 C69 C83 C97 C111 C125 C139 C153 C167 C181 C195 C209 C223zero 9,47E+05 9,96E+05 5,14E+05 5,65E+05 5,66E+05 5,17E+05 4,39E+05 3,73E+05 3,39E+05 3,15E+05 3,88E+05 5,02E+05 5,02E+05 3,88E+05 8,74E+05 9,15E+05

10 years 4,85E+01 4,93E+01 2,28E+02 2,48E+02 2,48E+02 2,28E+02 1,98E+02 1,71E+02 1,58E+02 1,48E+02 1,76E+02 2,23E+02 2,24E+02 1,80E+02 4,78E+01 4,85E+0150 years 8,93E-01 9,92E-01 2,28E-01 2,34E-01 2,35E-01 2,28E-01 2,21E-01 2,10E-01 2,11E-01 2,00E-01 2,03E-01 2,21E-01 2,27E-01 2,20E-01 7,88E-01 8,42E-0168 years 5,33E-01 6,16E-01 5,88E-02 6,17E-02 6,19E-02 5,88E-02 5,46E-02 5,06E-02 4,93E-02 4,67E-02 5,03E-02 5,73E-02 5,76E-02 5,15E-02 4,43E-01 4,87E-0177 years 4,75E-01 5,55E-01 4,50E-02 4,76E-02 4,76E-02 4,51E-02 4,13E-02 3,80E-02 3,66E-02 3,47E-02 3,81E-02 4,39E-02 4,39E-02 3,81E-02 3,91E-01 4,33E-01100 years 3,98E-01 4,66E-01 3,54E-02 3,75E-02 3,76E-02 3,56E-02 3,24E-02 2,98E-02 2,85E-02 2,71E-02 2,99E-02 3,46E-02 3,43E-02 2,95E-02 3,24E-01 3,60E-011000 years 4,43E-02 5,14E-02 1,92E-02 2,00E-02 2,00E-02 1,93E-02 1,80E-02 1,71E-02 1,66E-02 1,60E-02 1,70E-02 1,88E-02 1,87E-02 1,68E-02 3,64E-02 4,03E-0210000 years 8,74E-03 9,72E-03 8,35E-03 8,66E-03 8,66E-03 8,35E-03 7,95E-03 7,61E-03 7,44E-03 7,19E-03 7,56E-03 8,19E-03 8,19E-03 7,52E-03 7,53E-03 8,13E-03

Decay Heat (W/m3)BL FW

at t = 10 yearsMass below limit 1 W/m3 0,00E+00 0%

Mass below limit 10 W/m3 0,00E+00 0%Mass above limit 1,97E+05 100%

1,97E+05 100%at t ≥ 50 y

Mass below limit 1 W/m3 1,97E+05 100%Mass below limit 10 W/m3 0,00E+00 0%

Mass above limit 0,00E+00 0%1,97E+05 100%

limit < 2 mSv/h or 20 mSv/hAngle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341


10 years 3,79E+03 3,83E+03 1,60E+04 1,70E+04 1,70E+04 1,60E+04 1,46E+04 1,32E+04 1,28E+04 1,20E+04 1,32E+04 1,56E+04 1,58E+04 1,39E+04 3,77E+03 3,82E+0350 years 3,09E+01 3,19E+01 3,77E+01 3,80E+01 3,81E+01 3,74E+01 3,74E+01 3,64E+01 3,71E+01 3,52E+01 3,46E+01 3,65E+01 3,77E+01 3,84E+01 2,99E+01 3,06E+0168 years 7,87E+00 8,43E+00 4,46E+00 4,50E+00 4,51E+00 4,43E+00 4,41E+00 4,30E+00 4,35E+00 4,16E+00 4,12E+00 4,33E+00 4,45E+00 4,49E+00 7,23E+00 7,56E+0077 years 5,26E+00 5,74E+00 2,11E+00 2,14E+00 2,14E+00 2,10E+00 2,08E+00 2,03E+00 2,04E+00 1,97E+00 1,97E+00 2,06E+00 2,11E+00 2,10E+00 4,72E+00 4,98E+00100 years 2,83E+00 3,19E+00 1,03E+00 1,04E+00 1,04E+00 1,03E+00 1,01E+00 9,94E-01 9,85E-01 9,63E-01 9,77E-01 1,02E+00 1,02E+00 1,00E+00 2,45E+00 2,63E+001000 years 4,26E-01 4,62E-01 8,87E-01 8,94E-01 8,95E-01 8,87E-01 8,75E-01 8,67E-01 8,60E-01 8,44E-01 8,52E-01 8,76E-01 8,80E-01 8,69E-01 3,85E-01 4,05E-0110000 years 1,47E-01 1,50E-01 6,53E-01 6,59E-01 6,59E-01 6,53E-01 6,44E-01 6,37E-01 6,32E-01 6,20E-01 6,26E-01 6,44E-01 6,48E-01 6,38E-01 1,42E-01 1,44E-01

BL FWContact dose rate (mSv/h)

at t = 10 years at t = 77 yearsMass below limit 2 mSv/h 0,00E+00 0% Mass below limit 2 mSv/h 2,05E+04 10%

Mass below limit 20 mSv/h 0,00E+00 0% Mass below limit 20 mSv/h 1,76E+05 90%Mass above limit 1,97E+05 100% Mass above limit 0,00E+00 0%

1,97E+05 1,97E+05at t = 50 years at t = 100 y

Mass below limit 2 mSv/h 0,00E+00 0% Mass below limit 2 mSv/h 1,97E+05 100%Mass below limit 20 mSv/h 1,97E+05 100% Mass below limit 20 mSv/h 0,00E+00 0%

Mass above limit 0,00E+00 0% Mass above limit 0,00E+00 0%1,97E+05 1,97E+05



Work done for D1BL First Wall

Specific activity < 1 KBq/g

• No clearance, as expected.

• At t=100 y the recyclable fraction is 100%, if one considers decay heat and dose rate criteria. Using the operative limit on mass specific activity, the recycling fraction is 0%.

• The fraction might be, hence, lower or zero.

Remarks on BL-FW

Mass in kg

limit < 1000 Bq/gAngle 11 33 55 77 99 121 143 165 187 209 231 253 275 297 319 341


10 years 1,81E+07 2,00E+07 2,47E+10 2,72E+10 2,73E+10 2,48E+10 2,09E+10 1,76E+10 1,60E+10 1,49E+10 1,85E+10 2,42E+10 2,42E+10 1,86E+10 1,60E+07 1,71E+0750 years 1,11E+06 1,28E+06 3,23E+06 3,55E+06 3,56E+06 3,24E+06 2,76E+06 2,36E+06 2,16E+06 2,01E+06 2,45E+06 3,16E+06 3,15E+06 2,45E+06 9,31E+05 1,02E+06

100 years 6,05E+05 7,04E+05 5,31E+05 5,72E+05 5,72E+05 5,34E+05 4,73E+05 4,24E+05 4,00E+05 3,76E+05 4,31E+05 5,18E+05 5,15E+05 4,25E+05 4,96E+05 5,49E+051000 years 5,95E+04 6,97E+04 2,58E+05 2,74E+05 2,74E+05 2,59E+05 2,36E+05 2,18E+05 2,09E+05 1,98E+05 2,19E+05 2,52E+05 2,50E+05 2,14E+05 4,83E+04 5,38E+04

10000 years 7,90E+03 9,08E+03 1,13E+05 1,21E+05 1,21E+05 1,14E+05 1,02E+05 9,24E+04 8,77E+04 8,29E+04 9,36E+04 1,11E+05 1,10E+05 9,22E+04 6,49E+03 7,21E+03

BL FWSpecific Activity (Bq/g)

Up 100,000 y, mass > 1KBq/g = 1.97E+5



Work done for D1

• Component classification, @ 50 y

t=50yClearable SRM CRM PDW

component mass (kg) Activated mass generated (kg)blanket armour 5,45E+04 2,72E+05 0,00E+00 0,00E+00 0,00E+00 2,72E+05blanket FW 1,97E+05 9,83E+05 0,00E+00 0,00E+00 9,83E+05 0,00E+00blanket breeder 7,74E+06 3,87E+07 0,00E+00 0,00E+00 8,54E+06 3,01E+07blanket manifold 1,65E+06 8,24E+06 0,00E+00 0,00E+00 2,40E+06 5,84E+06HT shield 2,55E+06 1,27E+07 0,00E+00 0,00E+00 9,79E+06 2,94E+06LT shield 7,02E+06 7,02E+06 0,00E+00 0,00E+00 6,68E+06 3,45E+05vacuum vessel 1,16E+07 1,16E+07 0,00E+00 1,16E+07 0,00E+00 0,00E+00TF coils 1,80E+07 1,80E+07 1,54E+07 2,60E+06 0,00E+00 0,00E+00divertor structure 2,46E+06 2,46E+07 0,00E+00 0,00E+00 0,00E+00 2,46E+07divertor tiles 1,68E+05 1,68E+06 0,00E+00 0,00E+00 0,00E+00 1,68E+06total 5,14E+07 1,24E+08 1,54E+07 1,42E+07 2,84E+07 6,58E+07

12% 11% 23% 53%

Mass (kg)



Work done for D1

• Material classification, @ 50 y Clearable SRM CRM PDW

Eurofer 0,00E+00 0,00E+00 1,45E+07 3,66E+07W 0,00E+00 0,00E+00 0,00E+00 1,96E+06

LiPb 0,00E+00 0,00E+00 7,30E+06 2,74E+07WC 0,00E+00 0,00E+00 6,20E+06 3,20E+05

Boron 0,00E+00 9,51E+04 0,00E+00 0,00E+00316SS 0,00E+00 1,15E+07 0,00E+00 0,00E+00

ITER coil mixture 1,54E+07 2,60E+06 0,00E+00 0,00E+00total 1,54E+07 1,42E+07 2,80E+07 6,62E+07

12% 11% 23% 53%

Mass (kg)



Work done for D1

• Component classification, @ 100 y t=100 y

Clearable SRM CRM PDWcomponent mass (kg) Activated mass generated (kg)blanket armour 5,45E+04 2,72E+05 0,00E+00 0,00E+00 2,72E+05 0,00E+00blanket FW 1,97E+05 9,83E+05 0,00E+00 9,83E+05 0,00E+00 0,00E+00blanket breeder 7,74E+06 3,87E+07 0,00E+00 1,63E+07 2,23E+07 0,00E+00blanket manifold 1,65E+06 8,24E+06 0,00E+00 8,24E+06 0,00E+00 0,00E+00HT shield 2,55E+06 1,27E+07 0,00E+00 1,27E+07 0,00E+00 0,00E+00LT shield 7,02E+06 7,02E+06 0,00E+00 7,03E+06 0,00E+00 0,00E+00vacuum vessel 1,16E+07 1,16E+07 8,86E+06 2,70E+06 0,00E+00 0,00E+00TF coils 1,80E+07 1,80E+07 1,54E+07 2,60E+06 0,00E+00 0,00E+00divertor structure 2,46E+06 2,46E+07 0,00E+00 2,46E+07 0,00E+00 0,00E+00divertor tiles 1,68E+05 1,68E+06 0,00E+00 1,57E+06 1,13E+05 0,00E+00total 5,14E+07 1,24E+08 2,43E+07 7,68E+07 2,27E+07 0,00E+00

20% 62% 18% 0%

Mass (kg)



Work done for D1

• Material classification, @ 100 y Clearable SRM CRM PDW Total (kg)

Eurofer 0,00E+00 4,87E+07 2,32E+06 0,00E+00 5,11E+07

W 0,00E+00 1,57E+06 3,85E+05 0,00E+00 1,96E+06LiPb 0,00E+00 1,46E+07 2,00E+07 0,00E+00 3,47E+07WC 0,00E+00 6,52E+06 0,00E+00 0,00E+00 6,52E+06

Boron 7,29E+04 2,22E+04 0,00E+00 0,00E+00 9,51E+04316SS 8,79E+06 2,68E+06 0,00E+00 0,00E+00 1,15E+07

ITER coil mixture 1,54E+07 2,60E+06 0,00E+00 0,00E+00 1,80E+072,43E+07 7,68E+07 2,27E+07 0,00E+00 1,24E+08

20% 62% 18% 0%

Mass (kg)



Work done for D1

• Material classification, @ 100 y

0,00E+00

1,00E+07

2,00E+07

3,00E+07

4,00E+07

5,00E+07

6,00E+07

7,00E+07

8,00E+07

9,00E+07

[kg]

Eurofer W LiPb WC Boron 316SS ITER coilmixture

Total

ClearableSRM

CRM

Material

Ripartition of activated material @ 100 y

Clearable

SRM

CRM



Work done for D1

• Material classification, @ 100 y with LiPb reuse

Clearable SRM CRM PDW Total (kg)

Eurofer 0,00E+00 4,87E+07 2,32E+06 0,00E+00 5,11E+07

W 0,00E+00 1,57E+06 3,85E+05 0,00E+00 1,96E+06LiPb 0,00E+00 2,93E+06 4,00E+06 0,00E+00 6,93E+06WC 0,00E+00 6,52E+06 0,00E+00 0,00E+00 6,52E+06

Boron 7,29E+04 2,22E+04 0,00E+00 0,00E+00 9,51E+04316SS 8,79E+06 2,68E+06 0,00E+00 0,00E+00 1,15E+07

ITER coil mixture 1,54E+07 2,60E+06 0,00E+00 0,00E+00 1,80E+072,43E+07 6,51E+07 6,71E+06 0,00E+00 9,61E+07

25% 68% 7% 0%

Mass (kg)

Reduction of 22% of total, of 70% for CRM and of 15% for SRM.



Work done for D1Conclusive remarks• Lifetime components (TF, VV and LTS) at t = 100 y are clearable

for a share of 66%, the remainder 34% is recyclable, but 27% is > 1 kBq/g.

• For replaceable components recycling (SRM or CRM) is feasible according to the dose rate and decay heat criteria, but 100 % is >1 kBq/g, making it difficult, if meant for module re-fabrication.

• More detailed nodalization in the n-transport and activation calculation might reserve surprise and strongly reduce the estimated of recyclable material for replaceable components but not for lifetime components.

• LiPb reuse may reduce the total amount of activated material of 22%, with reduction of CRM quantity of 70%.

• A conservative approach based on clearance/recycling of lifetime components only, would lead to 30% cleared/recycled and 70% disposed of.

• Taking into account LiPb reuse, and effective recycling capability of ~50% of SRM and CRM, the cleared/recycled fraction would be ~70%.



Deliverable 6

• This deliverable will focus on the application of the RTI (Radio Toxicity Index) for defining clearance levels for radionuclides not included the IAEA Safety Guide No. RS-G-1.7, (but included in the former IAEA TECDOC-855).



Work done for D6

• Comparison between IAEA TECDOC-855 (1996) and IAEA Safety Guide No. RS-G-1.7 (2004) done in task TW5-TSW-002/D1. (for 56 nuclides)

56 nuclides for which, the derived unconditional clearance level was determined by waste handling scenarios and possible exposure pathways

Nuclide TECDOC 855 [Bq/g]

RS-G-1.7 [Bq/g]


RS-G-1.7 [Bq/g]


RS-G-1.7 [Bq/g]

H 3 3000 100 Y 90 300 1000 Au 198 3 10C 14 300 1 Nb 94 0,3 0,1 Tl 201 30 10Na 22 0,3 0,1 Tc 99m 30 100 Pb 210* 3 1Na 24 0,3 1 Tc 99 300 1 Po 210 3 1P 32 300 1000 Ru 106* 3 0,1 Th 228* 0,3 1S 35 3000 100 Ag 10m 0,3 0,1 Th 230 0,3 1Cl 36 300 1 Cd 109 300 1 Th 232 0,3 1Ca 45 3000 100 In 111 3 10 Ra 226* 0,3 1Cr 51 30 100 I 123 30 100 Ra 228* 0,3 1Mn 54 0,3 0,1 I 124 30 100 U 234 0,3 1Fe 55 300 1000 I 129 30 0,01 U 235* 0,3 1Fe 59 3 1 I 131 3 10 U 238* 0,3 1Co 57 30 1 Sb 124 0,3 1 Np 237* 0,3 1Co 58 3 1 Cs 134 0,3 0,1 Pu 239 0,3 0,1Co 60 0,3 0,1 Cs 137* 0,3 0,1 Pu 240 0,3 0,1Ni 63 3000 100 Ce 144* 30 10 Pu 241* 30 10Zn 65 0,3 0,1 Pm 147 3000 1000 Am 241 0,3 0,1Sr 89 300 1000 Eu 152 0,3 0,1 Cm 244 0,3 1Sr 90* 3 1 Ir 192 3 1* short lived daughters are taken into account



Work done for D6

Other 201 nuclides, given by IAEA Safety Guide No. RS-G-1.7, for which IAEA TECDOC-855 provides the values through the formula:

where: E is the effective energy in MeV and E is the effective energy in MeV, as given in ICRP Publication 38; ALIinh is the most restrictive value of the annual limit of intake by inhalation in Bq; and ALIing is the most restrictive value of the annual limit on intake by ingestion in Bq as given in ICRP Publication 61.



3

Work done for D6

2

Table 1. Values of Activity Concentration for Radionuclides of Natural Origin

[IAEA Safety Guide No. RS-G-1.7]

Table 2. Values of Activity Concentration for Radionuclides of Artificial Origin in Bulk

1

21 nuclides + 40KU-234 U-235 U-238 Th-232Th-230 Th-231 Th-234 Th-228Ra-226 Pa-231 Bi-210 Ac-228

Ac-227 Pb-210 Ra-228Th-227 Po-210 Ra-224Ra-223 Bi-212

Pb-212

257 nuclides

46 included in IAEA TECDOC-85510 included in

IAEA TECDOC-855



Work done for D6[IAEA Safety Guide No. RS-G-1.7] vs. [IAEA TECDOC-855]


IAEA SG N. RS-G-1.7 [Bq/g]











Be-7 20 10 Sr-85 1,9 1 Sb-122 2 10 Sm-151 500 1000 Tl-202 2,1 10 Pu-237 18 100F-18 0,99 10 Sr-85m 4,6 100 Sb-125 2,3 0,1 Sm-153 11 100 Tl-204 41 1 Pu-238 67 0,1Si-31 16 1000 Sr-87m 3,1 100 Te-123m 6,3 1 Eu-152m 2,8 100 Pb-203 3,1 10 Pu-242 65 0,1P-33 130 1000 Sr-91+ 1,3 10 Te-125m 21 1000 Eu-154 0,79 0,1 Pb-212+ 6,2 1 Pu-243 24 1000Cl-38 0,61 10 Sr-92 0,87 10 Te-127 37 1000 Eu-155 14 1 Bi-206 0,3 1 Pu-244 67 0,1K-40 4,8 10 Y-91 15 100 Te-127m 51 10 Gd-153 9 10 Bi-207 0,64 0,1 Am-242 28 1000K-42 2,3 100 Y-91m 1,9 100 Te-129 8,7 100 Gd-159 12 100 Bi-210 25 1 Am-242m 83 0,1K-43 1 10 Y-92 2,5 100 Te-129m 16 10 Tb-160 0,87 1 Bi-212+ 6,3 1 Am-243 17 0,1Ca-47 0,91 10 Y-93 4,8 100 Te-131 2 100 Dy-165 14 1000 Po-203 0,61 10 Cm-242 420 10Sc-46 0,49 0,1 Zr-93 520 10 Te-131m 0,69 10 Dy-166 18 100 Po-205 0,63 10 Cm-243 6,8 1Sc-47 8 100 Zr-95 1,3 1 Te-132 4,1 1 Ho-166 10 100 Po-207 0,77 10 Cm-245 9,8 0,1Sc-48 0,3 1 Zr-97+ 3,8 10 Te-133 0,79 10 Er-169 97 1000 At-211 25 1000 Cm-246 74 0,1V-48 0,34 1 Nb-93m 210 10 Te-133m 0,51 10 Er-171 2,4 100 Ra-223 7,1 1 Cm-247 3,3 0,1Mn-51 0,92 10 Nb-95 1,3 1 Te-134 1,1 10 Tm-170 26 100 Ra-224 97 1 Cm-248 1,7 0,1Mn-52 0,29 1 Nb-97+ 1,4 10 I-123 30 100 Tm-171 320 1000 Ra-225 20 10 Bk-249 300 100Mn-52m 0,39 10 Nb-98 3,6 10 I-126 2,2 10 Yb-175 11 100 Ra-227 4,9 100 Cf-246 320 1000Mn-53 550 100 Mo-90 1,2 10 I-130 0,46 10 Lu-177 19 100 Ac-227 3,2 1 Cf-248 330 1Mn-56 0,56 10 Mo-93 87 10 I-132 0,43 10 Hf-181 1,8 1 Ac-228 0,99 1 Cf-249 3 0,1Fe-52+ 1,3 10 Mo-99 5,4 10 I-133 1,5 10 Ta-182 0,77 0,1 Th-226+ 36 1000 Cf-250 91 1Co-55 0,49 10 Mo-101+ 0,66 10 I-134 0,37 10 W-181 24 10 Th-227 8,7 1 Cf-251 7,2 0,1Co-56 0,28 0,1 Tc-96 0,4 1 I-135 0,61 10 W-185 79 1000 Th-229 9,8 0,1 Cf-252 4,6 1Co-58m 240 10000 Tc-96m 22 1000 Cs-129 3,5 10 W-187 2,1 10 Th-231 24 1 Cf-253 120 100Co-60m 80 1000 Tc-97 82 10 Cs-131 42 1000 Re-186 19 1000 Th-234 67 1 Cf-254 50 1Co-61 7,3 100 Tc-97m 55 100 Cs-132 1,4 10 Re-188 7,4 100 Pa-230 1,4 10 Es-253 650 100Co-62m 0,36 10 Ru-97 4,1 10 Cs-134m 26 1000 Os-185 1,4 1 Pa-231 22 1 Es-254 0,59 0,1Ni-59 330 100 Ru-103 2 1 Cs-135 150 100 Os-191 21 100 Pa-233 4,2 10 Es-254m 2 10Ni-65 1,6 10 Ru-105+ 1,3 10 Cs-136 0,46 1 Os-191m 69 1000 U-230 150 10 Fm-254 330 10000Cu-64 4,9 100 Rh-103m 180 10000 Cs-138 0,4 10 Os-193 9,6 100 U-231 9,9 100 Fm-255 33 100Zn-69 31 1000 Rh-105 11 100 Ba-131 2,2 10 Ir-190 0,67 1 U-232 0,3 0,1Zn-69m+ 2,4 10 Pd-103 66 1000 Ba-140 4,7 1 Ir-194 5,8 100 U-233 290 1Ga-72 0,36 10 Pd-109+ 27 100 La-140 0,42 1 Pt-191 3,6 10 U-236 320 10Ge-71 210 10000 Ag-105 1,9 1 Ce-139 6,1 1 Pt-193m 100 1000 U-237 6,1 100As-73 46 1000 Cd-115 4,4 10 Ce-141 11 100 Pt-197 20 1000 U-239 11 100As-74 1,3 10 Cd-115m 11 100 Ce-143 3,2 10 Pt-197m 8,7 100 U-240+ 42 100As-76 1,9 10 In-113m 3,7 100 Pr-142 7,2 100 Au-199 8,3 100 Np-239 4,8 100As-77 33 1000 In-114m 9,7 10 Pr-143 31 1000 Hg-197 13 100 Np-240 0,77 10Se-75 2,6 1 In-115m 5,6 100 Nd-147 6,1 100 Hg-197m 8,7 100 Pu-234 110000 100Br-82 0,38 1 Sn-113 42 1 Nd-149 2,4 100 Hg-203 4 10 Pu-235 9,9 100Rb-86 6,1 100 Sn-125 2,5 10 Pm-149 20 1000 Tl-200 0,76 10 Pu-236 150 1

223 nuclides



Work done for D6As written in the Studsvik report [N-06/136]:RS-G-1.7 does not provide any method for calculating activity concentrations for not listed nuclides. Even if the number of derived values is much higher than in TECDOC 855 (279 nuclides vs. 56), there are still many not listed nuclides that may be of importance in the context of fusion waste clearance. In the present study Ar39, Hf178m, Hf178n, Cd113m, Sn121m and Ag108m are examples of such nuclides.The attempt to derive clearance levels for the missing radionuclides and compare them with the ones calculated by IAEA TECDOC-855 is shown, considering the relevant radionuclides in the context of fusion waste clearance. As an example we refer to some nuclides (Hf178m, Cd113m, Sn121m, Ag108m, Al26 and Be10).

The approach is based on the radiotoxicity index (RTI) already presented in previous studies and here briefly described.



Work done for D6

Definition of Radio Toxicity Index #1

• Uranium 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 and UO2), it might be used as a benchmark to compare fusion and fission power reactor radwaste.



Work done for D6

Definition of Radio Toxicity Index #2

• In this comparison assume U ore at 1% (˜100% U-238). U-238 specific activity = 1.24x107 Bq/kg. U ore (1% U-238) specific activity = 1.24x105 Bq/kg.

• The ingestion dose conversion factor of U-238, relevant to the public, is 4.50x10-8 Sv/Bq. Hence, the radio-toxicity of uranium ore (at 1%), is 5.60x10-3 Sv/kg.

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

Including U-235 and U-234, and decay products of U-238, U-235 and U-234, the specific activity of 1 kg of U ore at 1% would be 4.61x105 Bq/kg (factor 4). Considering the dose conversion factor for U-238, U-235 and U-234 and their decay products the related radio-toxicity would be 2.72 x10-2 Sv/kg (factor 5).



Work done for D6

RTI for PWR spent fuel (due to actinides) decreases with time, as Pu-239 has a “short” half-life, relative to that of U-238 (4.5 billion years). At ~ 480,000 y it becomes the same radio-toxicity of the natural U ore.

RTI for PWR spent fuel (actinides)

1E-02

1E-01

1E+00

1E+01

1E+02

1E+03

1E+04

1E+05

1E+06

0,0E

+0

5,0E

+4

1,0E

+5

1,5E

+5

2,0E

+5

2,5E

+5

3,0E

+5

3,5E

+5

4,0E

+5

4,5E

+5

5,0E

+5

Time [years]

Rad

io T

oxi

city

In

dex



Work done for D6According to table I of TECDOC 855 and using 5,60E-03 Sv/ kg as radiotoxicity for U ore

Nuclide Half Life, a

Lc, (IAEA TECDOC-855)

[Bq/g]

Lc,Bq/g (IAEA RS-G-1.7)

[Bq/g]

Sv/Bq for workers

Sv/Bq for members of the public

Radiotoxicity (Sv/kg)

RTI

U-238 4,47E+09 0,3 4,40E-08 4,50E-08 1,35E-05 2,4E-03U-238 4,47E+09 1,0 4,40E-08 4,50E-08 4,50E-05 8,0E-03

RTI = 0,001

Nuclide Half Life, a

Lc, (IAEA TECDOC-855)

[Bq/g]

Lc, calculated for RTI =

0,001

Sv/Bq for workers

Sv/Bq for members of the public

Radiotoxicity (Sv/kg)

Corresponding RTI

Ratio LcI AEA/LcRTI

Hf-178m 3,10E+01 1,0 1,2 4,70E-09 4,70E-09 4,61E-06 8,2E-04 0,82 Cd-113m 1,36E+01 73,0 0,2 2,30E-08 2,30E-08 1,68E-03 3,0E-01 299,95 Sn-121m 5,50E+01 120,0 14,7 3,80E-10 3,80E-10 4,56E-05 8,1E-03 8,15Ag-108m 1,27E+02 0,61 2,4 2,30E-09 2,30E-09 1,40E-06 2,5E-04 0,25

Al-26 7,16E+05 0,37 1,6 3,50E-09 3,50E-09 1,30E-06 2,3E-04 0,23Be-10 1,60E+06 40,00 5,1 1,10E-09 1,10E-09 4,40E-05 7,9E-03 7,86

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

Assuming

The approach with RTI = 0.001 criteria for clearance provides in general more conservative values than the calculated IAEA TECDOC-855

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