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Summary of RED-IMPACT results on the Impact of P&T on the High Level Waste Management E.M. Gonzalez (CIEMAT), on behalf of the RED-IMPACT collaboration 10 th International Exchange Meeting on Partitioning and Transmutation, IEMPT10 Mito


  1. Summary of RED-IMPACT results on the Impact of P&T on the High Level Waste Management E.M. Gonzalez (CIEMAT), on behalf of the RED-IMPACT collaboration 10 th International Exchange Meeting on Partitioning and Transmutation, IEMPT10 Mito (Japan) 6-10 October 2008 Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 1

  2. RED-IMPACT Impact of Partitioning, Transmutation and Waste Reduction Technologies on the Final Nuclear Waste Disposal KTH-Sweden: Coordinator 23 partners + 2 subcontractors FZJ-Germany: Co-Coordinator Belgium: BN; SCK-CEN Nuclear Industry & Czech Republic: NRI; RAWRA Utilities EC: ITU-Karlsruhe 32% France: Areva ANP, CEA; COGEMA Research Germany:FANP; GRS; IER; KKP 50% Netherlands: NRG Waste Agencies Romania: CITON 18% Slovakia: DECOM, VUJE Spain: CIEMAT; EA; ENRESA EC CONTRACT NO. FI6W-CT-2004-002408 UK: NexiaSolutions; NIREX; UC Duration: March 2004 – September 2007 Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 2

  3. RED-IMPACT After a comprehensive inventory of existing and foreseen nuclear fuel cycle facilities in Europe, including a review of worldwide ongoing R&D programs on P&T, and assuming the potential evolution of P&T technologies and advanced fuel cycles (including Gen III & Gen IV reactors and ADS), the project has estimated the effect of P&T on waste management when using existing deep geological repository designs. • WP1 : Review of waste management and transmutation strategies, selection of fuel cycles scenarios • WP2 : Feasibility of the industrial deployment of selected scenarios and their impact on waste management • WP3 : Assessment of waste streams, waste features, leach resistance, heat generation, reprocessing capability etc. for selected fuel cycles. • WP4 : Assessment of the benefits of P&T/C in advanced fuel cycles for waste management and geological disposal. • WP5: Economic, environmental and societal assessment of fuel cycle strategies • WP6: Synthesis and dissemination of results Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 3

  4. Scenarios for Fuel Cycles • Industrial scenarios @ equilibrium – Scenario A1: (reference) : once through open cycle with Gen- Scenario II / III reactors Variants & Time Dependent Scenarios – Scenario A2 : mono-recycling of plutonium in Gen-III reactors Mass flow (+ variants) Waste Strs: – Scenario A3 : Multirecycling of Pu (only) in Sodium Fast HLW, ILW,… Reactors (EFR) • Innovative scenarios @ equilibrium Isotopic V. – Scenario B1 : Multi-recycling of Pu & MA in Sodium Fast Heat, RdTx, Reactors (EFR) plus advanced PUREX RdAc, – Scenario B2 : mono-recycling of plutonium in Gen-III reactors Packages and burning of Minor Actinides in ADS plus advanced PUREX & PYRO Repository C – Scenario B3 : mono-recycling of plutonium in Gen-III reactors + burning of plutonium in Gen-IV fast reactors + burning of Volume Minor Actinides in ADS including advanced PUREX and PYRO (reduced efforts) P.A.: Doses • Transition Scenarios Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 4

  5. (NEA / Scenarios for Fuel Cycles Red-Impact) Scenario Variants & Time Dependent Scenarios Mass flow A2 A1 Waste Strs: HLW, ILW,… Isotopic V. B2 Heat, RdTx, RdAc, Packages Repository C B1 Volume P.A.: Doses A3 B3 Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 5

  6. Scenarios for Fuel Cycles Pu reprocessing in LWR (single) Only presently deployed actinide The reference cooling time is 50 years (Pu) recycle UO2 Initial enrichment in 235 U = 4.20% / HLW Waste Streams: MOX 8.5% Pu Irradiated U (enriched) Scenario Variants: MOX Spent fuel Variants & Time Dependent Scenarios Multiple recycling of Pu in LWR Purex HLW: Mass flow Different reactors and fuels for Pu recycling FF, 100% MA Different fuel burnup for Pu recycling U & Pu losses Waste Strs: Scenario A2 HLW, ILW,… U natural U natural U Depleted U Depleted Isotopic V. Enrichment Enrichment Heat, RdTx, 8.5%Pu MOX MOX UOX UOX Fabr. Fabr. RdAc, Fabr. Fabr. 4.20% 50GWd/THM Pu Pu 235U Packages Pu Pu UOX UOX MOX MOX Cooling: Cooling: Cooling: Cooling: PUREX PUREX PUREX PUREX irradiation irradiation irradiation irradiation Reproc. Reproc. Reproc. Reproc. 2 years 2 years in LWR in LWR 2 years 2 years in LWR in LWR Repository C 50GWd/THM MA, FP, Pu losses MA, FP, Pu losses Irr. MOX Irr. MOX Irradiated enriched U Irradiated enriched U Volume Storage Storage Storage Storage Irradiated Irradiated Storage Storage @ Surface 50 years depleted U depleted U P.A.: Doses 50 years Final HL Waste Final HL Waste Disposal Disposal @ Deep underground Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 6

  7. Scenarios for Fuel Cycles Generation IV fast reactor EFR CD9/91, Core, Axial and Radial Blankets 23.2% Pu and 2.7% MA in “MOX” Variants: Separate handling of FP heat sources (Cs+Sr) Scenario - 99% Cs & Sr separated from HLW - 99% Sr separated from HLW Variants & Time Dependent Scenarios - Increased FF loading of Univ. Canister (40 → 60 kg) - Increased FF loading + 99% Cs & Sr separated from HLW Mass flow - Increased FF loading + 99% Sr separated from HLW Waste Strs: HLW, ILW,… 2 years Pu + MA Scenario B1 U Depleted Isotopic V. 23.2% Pu, 2.7% MA Heat, RdTx, MOX MOX PUREX irradiation Storage RdAc, Reproc. Fabr. in LMFR 5 years Packages Fissil part : 136 GWd/tHM Irradiated U Depleted Axial blankets : 15 GWd/tHM Radial blankets : 24 GWd/tHM Repository C 45 years Storage HLW Waste Streams: Volume Irradiated U (depleted) Purex HLW: FP+ P.A.: Doses FF, Reprocessing Final Waste Losses U + Pu +MA MA, U, Pu losses Disposal Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 7

  8. Scenarios for Fuel Cycles Simplified double strata: with LWR UOX, Mono-recycling of PU in LWR and multi-recycling of Pu+MA in fast spectrun ADS (no Fast reactor) Variants: ADS with TRU Oxide fuel in ZrO 2 inert matrix (+ 8.5% Pu content in MOX and 5 years LWR UOX spent fuel cooling time) Separate handling of FP heat sources (Cs+Sr) (studied in B1) Scenario Variants & Time Dependent Scenarios Scenario B2 Mass flow Waste Strs: HLW, ILW,… Isotopic V. Heat, RdTx, RdAc, Packages Repository C Volume P.A.: Doses Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 8

  9. Packages 0.12 m 0.12 m 0.12 m Scenario Variants & Time Dependent Scenarios 0.7 m 0.7 m 0.7 m Mass flow 4.30 m 4.30 m 4.30 m 0.9 m 0.9 m 0.9 m Waste Strs: 4.54 m 4.54 m Spent Fuel: SPA HLW, ILW,… Isotopic V. HLW: Heat, RdTx, UC-V RdAc, Packages Repository C ILW: UC-C Volume P.A.: Doses Number of packages, volume and gallery length, heat and radiation levels (n, γ ) Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 9

  10. Deep Geological Repositories Scenario Variants & Time Dependent Scenarios Mass flow Waste Strs: HLW, ILW,… Granite Isotopic V. Czech Granite Spain Republic Heat, RdTx, RdAc, Packages Repository C Volume P.A.: Doses Salt Germany Boom Clay Belgium Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 10

  11. HLW: Waste Streams and Isotopic v. Red-Impact- HLW hypothesis Scenario Variants & Time Dependent Scenarios Mass flow Fractions of main chemical elements incorporated into the vitrified HLW (%) Waste Strs: SCENARIO SCENARIO A2 A2 A3 A3 B1 B1 B2 B2 HLW, ILW,… Standard Standard Standard Standard Extended Extended Extended Extended Extended Extended PYRO PYRO REPROCESSING TYPE REPROCESSING TYPE PUREX PUREX PUREX PUREX PUREX PUREX PUREX PUREX PUREX PUREX ZrN +TRUN ZrN +TRUN Blankets + Blankets + Blankets + Blankets + MOX MOX Isotopic V. UOX (PWR) UOX (PWR) UOX (PWR) UOX (PWR) REPROCESSED FUEL REPROCESSED FUEL Core (FR) Core (FR) Core (FR) Core (FR) (PWR) (PWR) (ADS) (ADS) 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 U and Pu U and Pu ACTINIDES ACTINIDES Heat, RdTx, (An) (An) 100 100 100 100 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 MA MA RdAc, 0 0 0 0 0 0 0 0 0 0 0 0 Noble Gases Noble Gases FISSION FISSION 1 1 1 1 1 1 1 1 1 1 1 1 Iodine Iodine PRODUCTS PRODUCTS Packages 100 100 100 100 100 100 100 100 100 100 0 0 Noble Metals Noble Metals (FP) (FP) 100 100 100 100 100 100 100 100 100 100 100 100 Others Others 0 0 0 0 0 0 0 0 0 0 0 0 Repository C H H LIGHT LIGHT 10 10 10 10 10 10 10 10 10 10 10 10 Carbon Carbon ELEMENTS ELEMENTS 1 1 1 1 1 1 1 1 1 1 1 1 Chlorine Chlorine Volume (Fuel Impurities) (Fuel Impurities) 100 100 100 100 100 100 100 100 100 100 100 100 Others Others Fuel Assembly Structurals Fuel Assembly Structurals P.A.: Doses 0 0 0 0 0 0 0 0 0 0 0 0 (particles) (particles) Zr of the ADS fuel matrix Zr of the ADS fuel matrix - - - - - - - - - - 1 1 (also for the Zr-fission product) (also for the Zr-fission product) Summary of RED-IMPACT results on the Impact of P&T… IEMPT10 / Mito (Japan) E.M. Gonzalez 11

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