Neutronic benchmark on the 2400 MW gas-cooled fast reactor design
Creators
- 1. NRG, Fuels, Actinides and Isotopes, P.O. box 25, 1755 ZG Petten (Netherlands)
- 2. CEA-Cadarache, DER/SPRC/LEDC, 13108 Saint-Paul-lez-Durance Cedex (France)
- 3. Nexia Solutions Ltd., Springfields, Preston, PR4 OXJ (United Kingdom)
- 4. Paul Scherrer Institut, 5232-Villigen (Switzerland)
Description
The 2400 MWth Gas-Cooled Fast Reactor (GCFR), with plate-type carbide/SiC CERCER fuel, is an innovative design exhibiting many attractive features among which sustainability achieved with an internal breeding gain close to zero and feedback coefficients enabling an excellent behavior under some safety transients. This paper summarizes the analytical results of an international benchmark exercise being set up within the European Union to verify the neutronic tools and associated nuclear data libraries currently used for helping in finalizing the design of the GCFR within the European Union. A rather simple homogenized 2D model has been specified for the first phase of this benchmark. The computational tools being used in the analysis include both a stochastic and a deterministic code, MCNP and ERANOS, respectively, with nuclear data essentially based on the JEF-2.2 data library. The overall results indicate that the agreement of the solutions provided by the different participants is satisfactory. The most significant discrepancy, which can be partly attributed to different ERANOS options, is observed in the case of the end of life reactivity and amounts to a few dollars. The rather positive outcome of this initial phase of the benchmark has allowed identifying deficiencies in the analytical tools and serves as a basis for the definition of subsequent phases. It might also help to identify potential ways to improve the design. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 10 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43129874
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BREEDING; DESIGN; DETERMINISTIC ESTIMATION; EUROPEAN UNION; FUEL PLATES; GCFR TYPE REACTORS; MATHEMATICAL SOLUTIONS; MIXED CARBIDE FUELS; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; REACTIVITY COEFFICIENTS; SILICON CARBIDES; STOCHASTIC PROCESSES
- Descriptors DEC
- BREEDER REACTORS; CALCULATION METHODS; CARBIDES; CARBON COMPOUNDS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; INTERNATIONAL ORGANIZATIONS; MATERIALS; NUCLEAR FUEL CONVERSION; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; SOLID FUELS
Optional Information
- Notes
- 7 refs.