VIP, an international programme of benchmark experiments for the study of Mixed oxides-fuelled cores
- 1. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)
Description
In the frame of two international programmes, in which Belgian Japanese and UK contractors were involved, a series of benchmarks experiments have been conducted in Venus, a pool-type critical facility built and operated by Belgian nuclear centre. Typical PWR and BWR assembly configurations were modelled, with and without mixed oxides fuel, and with a moderator density reduced to 73% or 51% of its nominal value. Axial buckling and detailed (pin-to-pin) fission density distributions were measured, and a few other parameters were investigated (spectral indices, reactivity effects of water level variations, ...). These experimental results are the reference for calibration of theoretical analyses performed by each partner in order to validate, and possibly improve, their theoretical predictions and studies for the power reactors. This paper includes the comparison of a few Belgian computational results with the corresponding experimental result. (authors). 5 figs., 1 tab
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Additional details
Publishing Information
- Imprint Title
- Reactor Physics and reactor computations
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 467-474.
- Report number
- INIS-mf--13907
Conference
- Title
- International conference on reactor physics and reactor computations.
- Dates
- 23-26 Jan 1994.
- Place
- Tel Aviv (Israel).
INIS
- Country of Publication
- Israel
- Country of Input or Organization
- Israel
- INIS RN
- 25044855
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENCHMARKS; BURNABLE POISONS; COMPUTERIZED SIMULATION; EVALUATED DATA; FISSION RATIO; FUEL ASSEMBLIES; GADOLINIUM; MIXED OXIDE FUELS; NUCLEAR CORES; POWER REACTORS; REACTOR CORES; REACTOR SIMULATORS; VENUS REACTOR
- Descriptors DEC
- ANALOG SYSTEMS; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; FUNCTIONAL MODELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; MATERIALS; METALS; NEUTRON ABSORBERS; NUCLEAR FUELS; NUCLEAR POISONS; NUMERICAL DATA; RARE EARTHS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SIMULATORS; SOLID FUELS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS