Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006.

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Presentation transcript:

Final Meeting TW5-TSW-001 Deliverable 2 SCKCEN, L. OomsCulham, October 23–24, 2006

PPCS Model AB FunctionMaterials PPCS Models Model A WCLL Model B HCPB Model AB HCLL Breeding LiPbBlanket Li 4 SiO 4 Blanket Be Blanket (n multiplier) S t r u c t u r e EUROFER Blanket In vessel shield Blanket Divertor In vessel shield HTS LTS Blanket (+ FW) SS 316VV ZrH HTS CuCrZrDivertor W Divertor (armour) WC LTS W alloy Divertor Co o l i ng Water Blanket Divertor VV LTS (cooling) He Blanket Divertor VV Blanket Divertor HTS

Model AB: Activation analysis R. Pampin UKAEA/ TW4-TRP-002 D2e, April 2005 ComponentReplacement schedule DivertorEach 2,5 years Blanket (incl. FW and armour)Each 5 years High Temperature ShieldEach 5 years Low Temperature ShieldLife time component (± 29 years) Vacuum VesselLife time component (± 29 years) TF CoilLife time component (± 29 years) ComponentT0T yearsT yearsT years BackFrontBackFrontBackFrontBackFront FW armour2.67E E E E-03 Blanket FW8.77E E E E-03 Blanket Breeder2.72E E E E E E E E-03 Blanket Manifold7.93E E E E-04 HTS5.85E E E E-04 LTS3.22E E E E-04 VV1.41E E E E-07 TF coil3.17E E E E-11 Divertor1.78E E E E E E E E-03 Dose rate Sv/h Replacement Schedule

Model AB: Activation analysis R. Pampin UKAEA/ TW4-TRP-002 D2e, April 2005 ComponentReplacement schedule DivertorEach 2,5 years Blanket (incl. FW and armour)Each 5 years High Temperature ShieldEach 5 years Low Temperature ShieldLife time component (± 29 years) Vacuum VesselLife time component (± 29 years) TF CoilLife time component (± 29 years) ComponentT0T yearsT yearsT years BackFrontBackFrontBackFrontBackFront FW armour2.67E E E E-03 Blanket FW8.77E E E E-03 Blanket Breeder2.72E E E E E E E E-03 Blanket Manifold7.93E E E E-04 HTS5.85E E E E-04 LTS3.22E E E E-04 VV1.41E E E E-07 TF coil3.17E E E E-11 Divertor1.78E E E E E E E E-03 Dose rate Sv/h Replacement Schedule

Time Scale Storage after irradiation Recycling of components separation recycling of materials refabrication and testing Storage awaiting reuse Reuse Stage 1: Temporary storage over a time period of maximum 5 years. The storage will be performed in the fusion plant and its major goal is to reduce the dose rate with 1 order of magnitude. Stage 2: Interim storage over a period of 100 years. The major goal for this on site storage is to reduce the dose rate (a few orders of magnitude) in order to perform off-site transportation. Stage 3: Final disposal (off site). Reference: A. Natalizio (ENSEC); In-vessel component storage, EFDA Task TW2-TRP-PPCS17 – Deliverable 4, dd Separation & recycling of materials (1 year). Refabrication & testing (1 to 2 years) Replacement scheme

Simulation of limits for HOR Limits defined in the past: 1000 Gq/g => 4 µSv/h => 6,4 mSv/y 10 µSv/h => 16 mSv/y (full exposure = 1600 h) Limits are very conservative (they meet the ICRP norm for the operators) The goal must not be to increase the limits (ALARA) A simulation with a reduced exposure confirms that materials must not be classified immediately in remote handling recycling if one applies: Shielding Reduced exposure Other measures to reduce the exposure of the operators First conclusion: 1.The limit for Hands On Recycling has to be kept at 10 µSv/h 2.Materials with a dose rate above 10µSv/h must not directly be classified as remote recycling

Simulation of limits for HOR Other remarks: 1.Using dose rates for limits between categories starting from HOR is much more logical than using specific activities. 2.On the contrary clearance based on 1 µSv/h has no sense, since pure beta-emitting isotopes can still exceed clearance limits. Therefore the principle of clearance index should be applied for those materials 3.Confinement of the workspace is inevitable, due to the Tokamak dust, Tritium…)

Remote Handling Facilities ► Dose rates of fusion components are acceptable for existing facilities ► The 5 years of temporary storage will reduce the dose rates of the components. ► But! What about build up after a second irradiation cycle ► The needed services are very specialised (testing and fabrication), precision ± 10 µm, ► Up to now only simple products were fabricated (melting) ► Confinement is unavoidable to protect the operators from internal contamination

Fusion classification

New proposal for Classification SRM is subdivided into two groups  Hands on recycling (dose rate up to 10 µSv/h)  Shielded recycling (dose rate between 10 µSv/h and 2 mSv/h) CRM + PDW becomes one group Remote Recycling (above 2 mSv/h) NAW (Clearance) is not defined by the dose rate of the materials but by the Clearance index. Clearance Ic < 1

Report: Precondition of the dose rate limits for recycling TW5-TSW-001 D2 SCKCEN: R-4377, , L. Ooms, S. Boden, S. Leblanc Draft available, final report after today’s discussion