Published September 1999
| Version v1
Book
A System of Neutronics Computational Benchmarks for VVER Reactors
- 1. Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)
- 2. DMT/SERMA CEA de Saclay, 91191 Gif-sur-Yvette (France)
- 3. Idaho National Engineering and Environmental Laboratory, MS-3885, P. O. Box 1625, Idaho Falls, IDAHO 83415-3885 (United States)
Description
A system of computational neutronic benchmarks has been developed over the last four years. This system is intended to complement the Atomic Energy Research (AER) benchmarks. This paper presents a summary of the development and a brief description of the benchmarks. The set is primarily comprised of interrelated benchmarks that share situation descriptions and data. The system covers the VVER 440 and VVER 1000 reactors extensively, and in a few cases the newer VVER 640 reactor design. Benchmarks within the system address the static, dynamic (with and without feedback), fuel depletion and fuel loading optimization, and normal as well as accident situations. (author)
Additional details
Publishing Information
- Publisher
- Senda Editorial S.A.
- Imprint Place
- Madrid (Spain)
- ISBN
- 84-699-0942-8
- Imprint Title
- M and C'99 - Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Imprint Pagination
- 2249 p.
- Journal Page Range
- p. 1823-1833
Conference
- Title
- Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Acronym
- M and C'99
- Dates
- 27-30 Sep 1999
- Place
- Madrid (Spain)
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- France
- INIS RN
- 54117086
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; NEUTRON TRANSPORT; NUCLEAR ENERGY; NUCLEAR FUELS; OPTIMIZATION; REACTOR DESIGN; WWER TYPE REACTORS
- Descriptors DEC
- DESIGN; ENERGY; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses