Nuclear fuels
Description
The nuclear fuel is one of the key component of a nuclear reactor. Inside it, the fission reactions of heavy atoms, uranium and plutonium, take place. It is located in the core of the reactor, but also in the core of the whole nuclear system. Its design and properties influence the behaviour, the efficiency and the safety of the reactor. Even if it represents a weak share of the generated electricity cost, its proper use represents an important economic stake. Important improvements remain to be made to increase its residence time inside the reactor, to supply more energy, and to improve its robustness. Beyond the economical and safety considerations, strategical questions have to find an answer, like the use of plutonium, the management of resources and the management of nuclear wastes and real technological challenges have to be taken up. This monograph summarizes the existing knowledge about the nuclear fuel, its behaviour inside the reactor, its limits of use, and its R and D tracks. It illustrates also the researches in progress and presents some key results obtained recently. Content: 1 - Introduction; 2 - The fuel of water-cooled reactors: aspect, fabrication, behaviour of UO2 and MOX fuels inside the reactor, behaviour in loss of tightness situation, microscopic morphology of fuel ceramics and evolution under irradiation - migration and localisation of fission products in UOX and MOX matrices, modeling of fuels behaviour - modeling of defects and fission products in the UO2 ceramics by ab initio calculations, cladding and assembly materials, pellet-cladding interaction, advanced UO2 and MOX ceramics, mechanical behaviour of the fuel assembly, fuel during a loss of coolant accident, fuel during a reactivity accident, fuel during a serious accident, fuel management inside reactor cores, fuel cycle materials balance, long-term behaviour of the spent fuel, fuel of boiling water reactors; 3 - the fuel of liquid metal fast reactors: fast neutrons radiation-induced damages in structural materials, fuels and targets for the transmutation in FBR; 4 - the fuel of gas-cooled reactors: fuel particulates, behaviour under irradiation, mechanical modeling, the fuel for very high temperature reactors, the fuel for gas-cooled fast reactors; 5 - the fuel for research reactors; 6 - the Jules Horowitz reactor: a tool for the future fuel studies. (J.S.)
Additional details
Additional titles
- Original title (French)
- Les combustibles nucleaires
Publishing Information
- Publisher
- Editions Le Moniteur
- Imprint Place
- Paris (France)
- ISBN
- 2-281-11325-9
- Imprint Pagination
- 151 p.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 39087193
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BWR TYPE REACTORS; CERAMICS; COATED FUEL PARTICLES; FABRICATION; FISSION PRODUCTS; FUEL ASSEMBLIES; FUEL MANAGEMENT; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; GCR TYPE REACTORS; JULES HOROWITZ REACTOR; LMFBR TYPE REACTORS; LOSS OF COOLANT; NUCLEAR FUELS; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; MANAGEMENT; MATERIALS; MATERIALS TESTING REACTORS; NUCLEAR MATERIALS MANAGEMENT; PELLETS; POOL TYPE REACTORS; POWER REACTORS; RADIATION EFFECTS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 125 refs.