Conceptual design of ASTRID fuel sub-assemblies
Creators
- 1. CEA Cadarache, DEN, DEC, F-13108 Saint-Paul-lez-Durance (France)
- 2. CEA Cadarache, DEN, DER, F-13108 Saint-Paul-lez-Durance (France)
- 3. AREVA-NP, 10 rue J. Récamier, 69456 Lyon Cedex 06 (France)
Description
Highlights: • The fuel sub-assembly design for the ASTRID CFV core is described. • Innovative design choices have been made to comply with the GEN IV objectives. • The heterogeneous and the large fuel pins contribute to a low sodium void worth. • The upper neutron shielding is removable from the S/A head before washing. - Abstract: The French 600 MWe Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) project has reached the end of its Conceptual Design phase. The core design studies are being conducted by the CEA with support from AREVA and EDF. Innovative design choices for the core have been made to comply with the GEN IV reactor objectives, marking a break with the former Phénix and SuperPhénix Sodium Fast Reactors. The main objective to improve safety compared with current GEN II or III reactors led to a core design that demonstrates intrinsically safe behaviour. A negative sodium void worth is achieved thanks to a new fuel sub-assembly design including (U,Pu)O2 and UO2 axially heterogeneous fuel pins, a large cladding/small spacer wire bundle, a sodium plenum above the fuel pins, and upper neutron shielding with both enriched and natural boron carbide (B4C) which also maintain a low secondary sodium activity level. As these Na-bonded B4C pins can lead to the retention of unacceptable amounts of sodium, the whole upper neutron shielding has been made removable on-line through the sub-assembly head just before the washing operations. Finite elements calculations have been performed to increase the stiffness of the stamped spacer pads in order to analyse its effect on the core mechanical behaviour during hypothetical radial core flowering and compaction events. More generally, all design choices for ASTRID have been made with the permanent objective of minimising the sub-assembly height to decrease the overall costs of the reactor and the fuel cycle. This paper describes the fuel sub-assembly design for the ASTRID CFV v4 core at the end of the Conceptual Design phase and studies performed to optimise the performances. Focus is placed on innovations and specificities in the design compared with former French SFRs.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.02.027Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.02.027;
- PII
- S0029-5493(17)30085-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 315
- Journal Page Range
- p. 51-60
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062618
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Descriptors DEI
- ACTIVITY LEVELS; AREVA NC; BORON CARBIDES; CEA; CLADDING; COST; ELECTRICITE DE FRANCE; FLEXIBILITY; FRANCE; FUEL ASSEMBLIES; FUEL CYCLE; FUEL PINS; MIXED OXIDE FUELS; NEUTRONS; PERFORMANCE; PHENIX REACTOR; REACTOR CORES; SHIELDING; SODIUM; SPACERS; SUPERPHENIX REACTOR; URANIUM DIOXIDE; VOIDS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALI METALS; BARYONS; BORON COMPOUNDS; BREEDER REACTORS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; DEPOSITION; DEVELOPED COUNTRIES; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; FRENCH ORGANIZATIONS; FUEL ELEMENTS; FUELS; HADRONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MECHANICAL PROPERTIES; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; SURFACE COATING; TENSILE PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES; WESTERN EUROPE
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.