PROMOX: The French R and D programme on MOX fuel
- 1. Fragema, 69 - Lyon (France)
- 2. Commissariat a l'Energie Atomique (France)
- 3. Electricite de France, Villeurbanne (France). Service Etudes et Projets Thermiques et Nucleaires
Description
To improve the knowledge of mixed oxide fuel rods behaviour, two prototype assemblies have been irradiated in the fourth core of the CAP reactor (Chaudiere Avancee Prototype) in Cadarache. The irradiation campaign started on the 29th of September 1985 and ended on the 2nd of July 1987, reaching 419 effective full power days, without any rod failure. The average burn-up of the MOX rods is evaluated at 20 GWd/tM, which is roughly equivalent to two commercial reactor cycles. Moreover, the reactor was operated under load following and frequency control mode. As a consequence, the MOX rods have undergone power cycles similar to those in an EDF commercial reactor. After irradiation, both assemblies were dismantled in the reactor handling and storage pool, and rods were shipped to CEN Saclay for post-irradiation examinations. This paper presents some preliminary results obtained on six MOX fuel rods examined in the hot cells of the LECI (Laboratoire d'Etude du Combustible Irradie). (author). 6 refs, 5 figs
Additional details
Publishing Information
- Imprint Title
- Recycling of plutonium and uranium in water reactor fuels
- Imprint Pagination
- 340 p.
- Journal Page Range
- p. 225-234.
- Report number
- IWGFPT--35
Conference
- Title
- Technical committee meeting on recycling of plutonium and uranium in water reactor fuels.
- Dates
- 13-16 Nov 1989.
- Place
- Cadarache (France).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22051882
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; GASES; MICROSTRUCTURE; MIXED OXIDE FUELS; PERFORMANCE TESTING; PLUTONIUM OXIDES; POST-IRRADIATION EXAMINATION; POWER DISTRIBUTION
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; DISTRIBUTION; ENERGY SOURCES; FLUIDS; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; SPATIAL DISTRIBUTION; TESTING; TRANSURANIUM COMPOUNDS