Impact of Transmutation Scenarios on Fuel Transportation
Creators
- 1. Commissariat a l'energie atomique et aux energies alternatives - CEA (France)
- 2. AREVA France (France)
- 3. Electricite de France - EDF (France)
Description
Minor actinides transmutation scenarios have been studied in the frame of the French Sustainable Radioactive Waste Management Act of 28 June 2006. Transmutation scenarios supposed the introduction of a sodium-cooled fast reactor fleet using homogeneous or heterogeneous recycling modes for the minor actinides. Americium, neptunium and curium (MA) or americium alone (Am) can be transmuted together in a homogeneous way embedded in FR-MOX fuel or incorporated in MA or Am-Bearing radial Blankets (MABB or AmBB). MA transmutation in Accelerator Driven System has also been studied while plutonium is being recycled in SFR. Assessments and comparisons of these advanced cycles have been performed considering technical and economic criteria. Transportation needs for fresh and used transmutation fuels is one of these criteria. Transmutation fuels have specific characteristics in terms of thermal load and neutron emissions. Thermal, radiation and criticality constraints have been taken into account in this study to suggest cask concepts for routine conditions of transport, to estimate the number of assemblies to be transported in a cask and the number of annual transports. Comparison with the no transmutation option, i.e. management of uranium and plutonium in SFRs, is also presented. Regarding these matters, no high difficulties appear for assemblies with limited content of Am (homogeneous or heterogeneous recycling modes). When fuels contain curium, technical transport uncertainties increase because of the important heat release requiring dividing fresh fuels and technological innovations development (MABB and ADS). (authors)
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47093719.pdf
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Additional details
Publishing Information
- Imprint Title
- Actinide and Fission Product Partitioning and Transmutation
- Imprint Pagination
- 417 p.
- Journal Page Range
- p. 71-78
- Report number
- NEA-NSC-R--2015-2
Conference
- Title
- 13. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
- Dates
- 23-26 Sep 2014
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 47093719
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; AMERICIUM; COMPUTERIZED SIMULATION; CRITICALITY; CURIUM; FEASIBILITY STUDIES; FUEL ASSEMBLIES; FUEL CYCLE; HEAT TRANSFER; MIXED OXIDE FUELS; RADIATION PROTECTION; RISK ASSESSMENT; SPECIFICATIONS; SPENT FUEL CASKS; SPENT FUELS; TRANSMUTATION; TRANSPORT
- Descriptors DEC
- ACTINIDES; CASKS; CONTAINERS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; REMOVAL; SIMULATION; SOLID FUELS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 10 refs.