High burnup effects on fuel behaviour under accident conditions: the tests CABRI REP-Na
Creators
- 1. Institut National des Sciences et Techniques Nucleaires (INSTN), Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
Description
A large, performance based, knowledge and experience in the field of nuclear fuel behaviour is available for nominal operation conditions. The database is continuously completed and precursor assembly irradiations are performed for testing of new materials and innovative designs. This procedure produces data and arguments to extend licensing limits in the permanent research for economic competitiveness. A similar effort must be devoted to the establishment of a database for fuel behaviour under off-normal and accident conditions. In particular, special attention must be given to the so-called design-basis-accident (DBA) conditions. Safety criteria are formulated for these situations and must be respected without consideration of the occurrence probability and the risk associated to the accident situation. The introduction of MOX fuel into the cores of light water reactors and the steadily increasing goal burnup of the fuel call for research work, both experimental and analytical, in the field of fuel response to DBA conditions. In 1992, a significant programme step, CABRI REP-Na, has been launched by the French Nuclear Safety and Protection Institute (IPSN) in the field of the reactivity initiated accident (RIA). After performing the nine experiments of the initial test matrix it can be concluded that important new findings have been evidenced. High burnup clad corrosion and the associated degradation of the mechanical properties of the Zircaloy-4 clad is one of the key phenomena of the fuel behaviour under accident conditions. Equally important is the evidence that transient, dynamic fission gas effects resulting from the close to adiabatic heating introduces a new explosive loading mechanism which may lead to clad rupture under RIA conditions, especially in the case of heterogeneous MOX fuel. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 270
- Journal Issue
- 1-2
- Journal Page Range
- p. 55-64
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30033233
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CORROSION; CRACKS; CREEP; EMBRITTLEMENT; FISSION PRODUCTS; HYDROGENATION; NUCLEAR FUELS; OPTICAL MICROSCOPY; PLUTONIUM COMPOUNDS; RADIATION EFFECTS; REACTOR ACCIDENTS; URANIUM COMPOUNDS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHEMICAL REACTIONS; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; RADIOACTIVE MATERIALS; REACTOR MATERIALS; TRANSITION ELEMENT ALLOYS; TRANSURANIUM COMPOUNDS
Optional Information
- Notes
- 9 refs.