LWR MOX fuel experience in Belgium and France with special emphasis placed on the results obtained in the BR3 PWR
- 1. Societe Belge pour l'Industrie Nucleaire, Brussels
- 2. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)
- 3. Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy, Villacoublay (France)
- 4. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)
Description
MOX fuel has been developed since 1958, first on a laboratory scale, later at the pilot level and finally to an industrial operation stage. This progressive approach to maturity has resulted in improvement of the fabrication processes, leading to an appropriate fuel, and collection of the database required to qualify the fuel for scheduled operation. The key to success has been the experience built up through fabrication of large quantities of MOX fuel and irradiation of experimental or characterized fuel assemblies in various PWRs and BWRs. In particular, MOX fuel rods manufactured by BELGONUCLEAIRE (BN) following two fabrication processes (mechanical blending and micronized master blend powder) were irradiated in the BR3 PWR under various steady state operating conditions. Surveillance and post-irradiation examination of MOX fuels from BR3, CNA, Dodewaard and Garigliano are already providing the performance references required. The main conclusions can be summarized as follows: (1) MOX fuel is now fabricated industrially at the same quality level as U fuel; (2) MOX fuel irradiation behaviour is superior to that of U fuel; (3) an adequate database already exists for the actual irradiation conditions in LWR power plants. The R and D programme is being pursued in a timely manner to acquire, for steady state and transient operating conditions, the expanded database required for the more demanding irradiation conditions contemplated in the future. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-050087-0
- Imprint Title
- Improvements in water reactor fuel technology and utilization
- Imprint Pagination
- 621 p.
- Series
- Proceedings series.
- Journal Page Range
- p. 363-383.
Conference
- Title
- International symposium on improvements in water reactor fuel technology and utilization.
- Dates
- 15-19 Sep 1986.
- Place
- Stockholm (Sweden).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 18083110
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; DEFORMATION; FABRICATION; FISSION PRODUCT RELEASE; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; MIXED OXIDE FUELS; PERFORMANCE TESTING; PLUTONIUM DIOXIDE; POWER DENSITY; PWR TYPE REACTORS; REPROCESSING; SOLUBILITY; TRANSIENTS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; TESTING; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 22 refs, 11 figs, 5 tabs.
- Secondary number(s)
- IAEA-SM--288/38.