VALMOX: Validation of Nuclear Data for High Burn-up MOX Fuels
Description
VALMOX is one of the projects of the cluster EVOL (Evolutionary Fuel Concepts: High Burn-up and MOX Fuels), which is part of the research programme on Nuclear Energy, Safety of the Existing Installations. Four companies are engaged in this work. Entirely devoted to MOX assemblies in Light Water Reactors, VALMOX comprises the evaluation of the actinide and fission product inventory of MOX fuel at high burn-up (typically 60 GWd/t), with special attention to the helium production. Calculated values for the spent fuel isotopic masses are to be compared to the measured ones, with sensitivity analyses made in support. JEF-2.2 nuclear data is taken as a basis for the calculations. The resulting recommendations on nuclear data should be employed in the preparation and testing of the next JEFF-3.1 file. The VALMOX work is based on the best available analyses of spent, commercial MOX fuel, for burn-up of 60 GWd/t and higher. It includes MOX irradiations data from Saint-Laurent-des-Eaux and Dampierre (CEA) and data from the ARIANE programme (BN and SCK-CEN). SCK-CEN is responsible for the MC calculation of the ARIANE irradiation experiments which took place from 1990 to 1996 in the 400-MWe PWR of Beznau-1
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Additional details
Identifiers
Publishing Information
- Publisher
- Belgian Nuclear Research Center SCK-CEN
- Imprint Place
- Mol (Belgium)
- Imprint Title
- Scientific Report 2004
- Imprint Pagination
- 186 p.
- Journal Page Range
- p. 42-43
- Report number
- INIS-BE--0009
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 36097535
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Progress Report, Numerical Data
- Descriptors DEI
- BEZNAU-1 REACTOR; BURNUP; EVALUATED DATA; HELIUM; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; PROGRESS REPORT; WATER COOLED REACTORS
- Descriptors DEC
- DATA; DOCUMENT TYPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUIDS; FUELS; GASES; INFORMATION; MATERIALS; NONMETALS; NUCLEAR FUELS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; RARE GASES; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- The abstract is a contribution to the 2004 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN