Study on recycling of fusion Study on recycling of fusion activated materials: activated materials: Identify activation levels, Identify activation levels, characteristics and decay time characteristics and decay time requirements of irradiated material requirements of irradiated material (deliverable 3) (deliverable 3) R Pampin R Pampin , R Bestwick , R Bestwick EURATOM/UKAEA Fusion Association EURATOM/UKAEA Fusion Association AMEC-NNC Ltd AMEC-NNC Ltd TW5-TSW-001 monitoring meeting TW5-TSW-001 monitoring meeting CEN-SCK Mol, June 2006 CEN-SCK Mol, June 2006
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R Pampin , R Bestwick EURATOM/UKAEA Fusion Association AMEC-NNC Ltd
TW5-TSW-001 monitoring meeting CEN-SCK Mol, June 2006. Study on recycling of fusion activated materials: Identify activation levels, characteristics and decay time requirements of irradiated material (deliverable 3). R Pampin , R Bestwick EURATOM/UKAEA Fusion Association AMEC-NNC Ltd. - PowerPoint PPT Presentation
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Study on recycling of fusion activated materials:Study on recycling of fusion activated materials:
Identify activation levels, characteristics and Identify activation levels, characteristics and decay time requirements of irradiated materialdecay time requirements of irradiated material
(deliverable 3)(deliverable 3)
R PampinR Pampin, R Bestwick, R Bestwick
EURATOM/UKAEA Fusion AssociationEURATOM/UKAEA Fusion Association
AMEC-NNC LtdAMEC-NNC Ltd
TW5-TSW-001 monitoring meeting TW5-TSW-001 monitoring meeting CEN-SCK Mol, June 2006CEN-SCK Mol, June 2006
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 2/13
BackgroundBackground
European Fusion Programme strategy for fusion irradiated waste:
Release from regulatory control of mildly activated material, usually lifetime, bulky, outer components: TFC, VV, LTS
Recycle within the nuclear industry (fission/fusion) the rest
PPCS radioactive waste results: all material cleared/recycled within 100 years, but:
Lack of detail in the models (e.g. outer components)
Inadequate modelling of particular materials (e.g. LiPb)
Recycling criteria based on radiological parameters only, which were imprecise and over-conservative.
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 3/13
BackgroundBackground
PPCS recycling criteria: some sensible for certain waste streams following certain routes (e.g. re-melting of steels); “complex recycling” limit is crucial but:
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 9/13
Preliminary resultsPreliminary results
Cooling times of PPCS-AB and PPCS-B individual constituents and materials and average components; in preparation.
PPCS-AB IB TFC 2 mSv/h 0.01 mSv/h
rear case < 1y < 1y
rad plates < 1y 25y
front case 1y 45y
SC strand < 1y 10y
incoloy <1y 35y
epoxy-glass < 1y < 1y
average < 1y 30y
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 10/13
Preliminary resultsPreliminary results
PPCS-AB results (general):
Ex-vessel: most materials, individually or as TFC, VV and LTS, show contact dose rates < 2 mSv/h (earlier OB than IB).
Ex-vessel: many of these show < 0.01 mSv/h after suitable decay time (few years OB, several decades IB).
In-vessel: poloidal variation is negligible.
In-vessel: all Eurofer and LTS neutron shield (WC) show contact dose rates < 2 mSv/h after ~75 years.
In-vessel: LiPb breeder and W armour still exceed 2 mSv/h after 100 years:
Dominant nuclides arise from Pb and W isotopes, hence impurity control not very useful in this case! isotopic separation seems imperative reuse in fusion plant?
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 11/13
PM-AB contact dose rates - outboard
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
0 1 10 100 1000time (y)
cont
act
dose
rat
e (S
v/h)
1 cycle LiPb5 cycles LiPbpure Pb
Preliminary resultsPreliminary results
PPCS-AB results: W and LiPb PPCS specifications contain many impurities: (a) manufacturer limits, (b) detection limits.
PM-AB contact dose rates - outboard
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
0 1 10 100 1000time (y)
cont
act
dose
rat
e (S
v/h)
ppcs w 5 FPY
ppcs w 1 FPY
pure w 5 FPY
Co, Ni, Nb, Mo, Eu, Sm, Gd, Tb, Pt, Ir, Pb, U, Th, Bi, Ag, Cd, Ba, Tl, Co, Nb
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 12/13
Preliminary resultsPreliminary results
PPCS-B results (general):
In-vessel: again, all Eurofer and LTS neutron shield (ZrH) show < 2 mSv/h in ~75 years.
In-vessel: Li4SiO4, Be and W armour, however, do not meet this target Li4SiO4 and Be dose entirely due to impurities:
control of these would meet target
PMB contact dose rates - outboard
1.E-05
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
0 1 10 100 1000time (y)
cont
act
dose
rat
e (S
v/h)
ppcs li4sio4pure li4sio4ppcs bepure be
Co, Ni, Nb, Mo, Eu, Sm, Gd, Tb, Pt, Ir, Pb, U, Th, Bi, Ag,
Cd, Ba, Tl, Co, Nb
TW5-TSW-001 monitoring meeting, CEN-SCK Mol, Belgium, June 2006 13/13
SummarySummary
Upgrading PPCS work on PPCS-AB and PPCS-B radioactive waste analysis using recent regulations, new nuclear data, improved modelling and realistic recycling scenarios.
Assess clearance/recycling potential and interim decay times.
Results:
new IAEA levels increase amount of material to recycle.
PPCS analyses over-conservative: most material suitable for “simple-recycling” after < 75y cooling time.
control of impurities crucial, not only in steels but also for e.g. Be and Li4SiO4: requirements being developed.
Further input: definition of “non-simple” recycling routes and radiological criteria.
Draft report & radiological data available shortly