MOX fuel fabrication: Technical and industrial developments
Creators
- 1. COMMOX, Villacoublay (France)
- 2. COMMOX, Bruxelles (Belgium)
Description
The plutonium available in the near future is generally estimated rather precisely on the basis of the reprocessing contracts and the performance of the reprocessing plants. A few years ago, decision makers were convinced that a significant share of this fissile material would be used as the feed material for fast breeder reactors (FBRs) or other advanced reactors. The facts today are that large reprocessing plants are coming into commercial operations: UP3 and soon UP2-800 and THORP, but that FBR deployment is delayed worldwide. As a consequence, large quantities of plutonium will be recycled in light water reactors as mixed oxide (MOX) fuels. MOX fuel technology has been properly demonstrated in the past 25 years. All specific problems have been addressed, efficient fabrication processes and engineering background have been implemented to a level of maturity which makes MOX fuel behaving as well as Uranium fuel. The paper concentrates on todays MOX fabrication expertise and presents the technical and industrial developments prepared by the MOX fuel fabrication industry for this last decade of the century
Additional details
Publishing Information
- Publisher
- World Nuclear Fuel Market.
- Imprint Place
- Norcross, GA (United States)
- Imprint Title
- World nuclear fuel market. Seventeenth annual meeting
- Imprint Pagination
- 208 p.
- Journal Page Range
- p. 103-109.
Conference
- Title
- 17. World Nuclear Fuel Market (WNFM) annual meeting and international conference on nuclear energy.
- Dates
- 14-16 Oct 1990.
- Place
- Toulouse (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059252
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AVAILABILITY; BWR TYPE REACTORS; CAPACITY; DECONTAMINATION; DEPLETED URANIUM; DESIGN; ECONOMICS; EFFICIENCY; FABRICATION; FUEL FABRICATION PLANTS; FUEL MANAGEMENT; FUEL REPROCESSING PLANTS; HOMOGENEOUS MIXTURES; IMPURITIES; MARKETING; MIXED OXIDE FUELS; NATURAL URANIUM; OPERATION; PLUTONIUM; POROSITY; POWDERS; PWR TYPE REACTORS; QUALITY ASSURANCE; RADIATION PROTECTION; RADIOACTIVE WASTES; REACTOR CORES; REGULATIONS; RELIABILITY; REPROCESSING; SENSITIVITY; SOLUBILITY; SPECIFICATIONS; SPENT FUELS; SURFACE PROPERTIES; TRANSPORT
- Descriptors DEC
- ACTINIDES; BUSINESS; CLEANING; DISPERSIONS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; LAWS; MANAGEMENT; MATERIALS; METALS; MIXTURES; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9010111--.