The REBUS Experimental Programme for Burn-Up Credit
Creators
- 1. SCK.CEN, Boeretang 200, 2400 Mol (Belgium)
- 2. Belgonucleaire (Belgium)
Description
An international programme called REBUS (Reactivity tests for a direct evaluation of the Burn-Up credit on Selected irradiated LWR fuel bundles) for the investigation of the burn-up credit has been initiated by the Belgian Nuclear Research Center SCK.CEN and Belgonucleaire with the support of USNRC, EdF from France, VGB, representing German nuclear utilities and NUPEC, representing the Japanese industry. The programme aims to establish a neutronic benchmark for reactor physics codes. This benchmark will qualify the codes to perform calculations of the burn-up credit. The benchmark exercise investigates the following fuel types with associated burn-up: - Reference 3.3% enriched UO2 fuel; - Fresh commercial PWR UO2 fuel; - Irradiated commercial PWR UO2 fuel (51 GWd/tM); - Fresh PWR MOX fuel; - Irradiated PWR MOX fuel (20 GWd/tM). Reactivity effects are measured in the critical facility VENUS. Fission rate and flux distributions in the experimental bundles will be determined. The accumulated burn-up of all rods is measured non-destructively in a relative way by gross gamma-scanning, while some rods are examined by gamma-spectrometry for an absolute determination of the burn-up. Some rods will be analyzed destructively with respect to accumulated burn-up, actinides content and TOP-19 fission products (i.e. those non-gaseous fission products that have most implications on the reactivity). Additionally some irradiated rods have undergone a profilometry and length determination. The experimental implementation of the programme has started in 2000 with major changes in the VENUS critical facility. Gamma scans, profilometry, length determination and gamma-spectrometry measurements on the MOX fuel have been performed. In the course of October 2001 the first fresh fuel configuration will be investigated. In the same period the commercial irradiated fuel will arrive at the SCK.CEN hot cells and will be re-fabricated into fuel rodlets of 1 meter length. (authors)
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers - ASME
- Imprint Place
- New York (United States)
- Imprint Pagination
- 8 p.
Conference
- Title
- 10. international conference on nuclear engineering
- Acronym
- ICONE-10
- Dates
- 14-18 Apr 2002
- Place
- Arlington - Virginia (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39079606
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; FISSION; FISSION PRODUCTS; FUEL ELEMENT CLUSTERS; GAMMA SPECTROSCOPY; IRRADIATION; MIXED OXIDE FUELS; PWR TYPE REACTORS; REACTIVITY; REACTOR PHYSICS; SPENT FUELS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; NUCLEAR REACTIONS; OXIDES; OXYGEN COMPOUNDS; PHYSICS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SOLID FUELS; SPECTROSCOPY; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS