Spent Fuel Management and Storage in Germany

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Spent Fuel Management and Storage in Germany A. Jussofie GNS, Essen International Seminar on Interim Storage of Spent Fuel Seite 1

Nuclear power plants (NPP) in Germany 82 Mio inhabitants 357,104 km 2 In total: 17 active NPP Thereof: 11 PWR and 6 BWR 450 tons annual discharge of spent fuel NPP in operation/on-site SFSF NPP cut-off or closed-down NPP completely dismantled Reseach/waste treatment plant Centralized dry SFSF 1 2 3 L/ILW: Final repository Operating plan licence 2007 Emplacement stopped HLW; exploration phase Seite 2

Energy mix in Germany status 2009 Water 3.2 % Wind 6.3 % Others 12.1% 22.6 % Nuclear energy Electrical power produced 2009 ca. 135 TWh Natural gas 12.9 % 24.6 % Brown coal Anthracite coal 18.3 % Seite 3

Disposal route in Germany Spent Fuel Assemblies (SFA) from NPP Reprocessing Sole disposal route up to the 1980/90s Since June 2005 any delivery of SFA to a reprocessing plant is prohibited. Completion of the reprocessed waste return is expected in 2024. Direct Disposal Sole potential disposal route since June 2005 Development began in 1970s as so-called reference concept Completion of the pilot conditioning plant (Pilotkonditionierungsanlage, PKA) in 2000 Today s policy: Once through nuclear fuel cycle Seite 4

Disposal of spent fuel assemblies (SFA) in Germany Spent fuel assemblies About 6,400 t HM About 10,000 t HM Intermediate Storage Central and decentralized on-site-dry-storage facilities MOX Waste from Reprocessing Reprocessing Conditioning Pilot conditioning plant Final repository Seite 5

Return of waste from reprocessing plants The reprocessed spent fuel (about 6,000 t HM) yields the following waste types and amounts: Reprocessing plant Spent fuel reprocessed Casks Waste type Number of casks Return period AREVA-NC TS 28V, CSD-V 108 until 2011 5,309 t CASTOR HAW20/28CG, TN85, CASTOR HAW28M TGC 36 HLW CSD-C 150 from 2015 CSD-V CSD-B LLW vitrified ILW vitrified CASTOR HAW28M CSD-B ILW 20 from 2014 CSD-C NDA 768 t CASTOR HAW28M HLW 21 from 2014 Compacted hulls, endpieces Seite 6

New development: CASTOR HAW28M 2010-2011 Loading of 22 casks Dimensions: Cask Weight loaded: Loading: Inventory: Max. Heat Load: Total Activity: H = 6120 mm, Ø = 2430 mm 114.3 t max. 28 canisters with vitrified HLW 55 GWd/MGHM - equivalent 56 kw 1270 PBq Seite 7

Storage hall for the HLW-casks returned to Gorleben 1 st transport to Gorleben: May 1996 Vitrified HLW-Waste currently from France, from 2014 from United Kingdom: centralized storage at Gorleben Compacted hulls and endpieces: planned for centralized storage at Ahaus 75 CASTOR HAWcasks 7500 t 1 Eiffel Tower Since 2009 additional 11 TN85-casks Seite 8

Accumulation of spent fuel Total amount SFA t HM - Accumulated by 31 Dec 2009 17,300 5,700 in reactor pools and dry storage Intermediate storage in about 1,000 transport-/ storage casks without considering the extension of reactor life time Final repository - Reference concept POLLUX about 2,000 casks - Fuel rod container BSK3 about 6,800 containers Seite 9

CASTOR Casks used for Spent Fuel Storage CASTOR V/19 Dimensions: H = 5860 mm, Ø = 2440 mm Cask Weight Loaded: 125.6 t max. Capacity: 19 PWR F.A. Max. Initial Enrichment: 4.45 wt % U-235 Max. Average Burn-up: 65 GWd/MTHM Max. Heat Load: 39 kw Total Activity: 5.5 E+17 Bq CASTOR V/52 Dimensions: H = 5450 mm, Ø = 2440 mm Cask Weight Loaded: 123.4 t max. Capacity: 52 BWR F.A. Max. Initial Enrichment: 4.6 wt % U-235 Max. Average Burn-up: 65 GWd/MTHM Max. Heat Load: 40 kw Total Activity: 1.2 E+18 Bq Seite 10

Loading of a CASTOR V-casks Text Seite 11

Intermediate storage of CASTOR -casks filled with SFA Total Ahaus Gorleben Biblis Neckarwestheim Philippsburg Emsland Gundremmingen Krümmel Grafenrheinfeld Isar Grohnde Brokdorf Brunsbüttel Unterweser 6 5 6 5 13 16 12 12 17 28 25 32 31 41 Status: 31th December 2009 249 2 centralized dry storage facilities Ahaus & Gorleben 12 + 3 decentralized storage facilities onsite near NPP 12 on-site intermediate dry storage facilites with 1435 storing positions Seite 12

Pilot Conditioning Plant (PKA) at Gorleben TSC TSC without secondary lid Fuel elements Staff recreation area 1. Unloading cell Area for cask handling Fuel rods Cans with fuel rods 2. Disassembling cell POLLUX POLLUX with welded lid Three hot cells 3. Loading cell PKA-building Handling sequence at the PKA Seite 13

Hot cells of Pilot Conditioning Plant Disassembling Unloading Loading Seite 14

POLLUX -Reference concept POLLUX - cask Disposal system 5 t HM 10 PWR-FA 60 t Underground transportation Concept status: end of 1990s Aboveground disposal tests Seite 15

Additional Disposal Concepts for SFA Reference concept Additional concepts POLLUX BSK 3 DIREGT Intermediate storage in CASTOR V CASTOR V CASTOR V Conditioning after intermediate storage Reloading Transfer to the final repository POLLUX Disassembling of SFA BSK 3 Transfer cask Whole SFA CASTOR V Emplacement in Drift BSK 3 Borehole (BSK 3) Borehole Status Aboveground testing finished in 2000, basis for repository layout Aboveground testing finished in 2009 Feasibility studies ongoing Seite 16

Way ahead Resumption of exploration work of the salt dome in Gorleben 2010-2015 Development of a site related suitability statement 2015-2016 Decision on site 2019 Planning of the final repository layout and plan submission from 2020 Finishing of the plan approval procedure 2028 Construction until operational start 2035 Start of the final disposal at the earliest 2035 1977 1979 1985 2000 2010 2028 2035 58 years! Seite 17

Conclusion The reprocessing of spent fuel is technologically mature and well experienced but was prohibited by the German AtG. There are proved procedures for transport, intermediate storage and the conditioning of spent fuel. The disposal of spent fuel is technologically already solved to a large extent. The exploration results obtained so far strongly suggest that the salt dome of Gorleben is suitable to host a repository for heatgenerating waste and spent fuel. The political decision on resuming the exploration of the salt dome in Gorleben and commissioning the first tentative safety analysis are important steps to move ahead on the way to a deep geological repository for heat-generating HLW. A concept for an appropriate participation of the public would be desirable. Seite 18