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Vitanza, C.; Hrehor, M.
Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Committee on the safety of nuclear installations - CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)2006
Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Committee on the safety of nuclear installations - CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)2006
AbstractAbstract
[en] This document is intended to provide regulators, their technical support organizations and industry with a concise review of existing fuel experimental data at RIA and LOCA conditions and considerations on how these data affect fuel safety criteria at increasing burn-up. It mostly addresses experimental results relevant to BWR and PWR fuel and it encompasses several contributions from the various experts that participated in the CSNI SEGFSM activities. It also covers the information presented at the joint CSNI/CNRA Topical Discussion on high burn-up fuel issues that took place on this subject in December 2004. The report is organized in the following way: the CABRI RIA database (14 tests), the NSRR database (26 tests) and other databases, RIA failure thresholds, comparison of failure thresholds for the HZP case, LOCA database ductility tests and quench tests, LOCA safety limit, provisional burn-up dependent criterion for Zr-4. The conclusions are as follows. On RIA, there is a well-established testing method and a significant and relatively consistent database from NSRR and Cabri tests, especially on high burn-up Zr-2 and Zr-4 cladding. It is encouraging that several correlations have been proposed for the RIA fuel failure threshold. Their predictions are compared and discussed in this paper for a representative PWR case. On LOCA, there are two different test methods, one based on ductility determinations and the other based on 'integral' quench tests. The LOCA database at high burn-up is limited to both testing methods. Ductility tests carried out with pre-hydrided non-irradiated cladding show a pronounced hydrogen effect. Data for actual high burn-up specimens are being gathered in various laboratories and will form the basis for a burn-up dependent LOCA limit. A provisional burn-up dependent criterion is discussed in the paper
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28 Nov 2006; 41 p; 38 refs.
Record Type
Report
Literature Type
Numerical Data
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BURNUP, BWR TYPE REACTORS, CABRI REACTOR, CLADDING, COMPARATIVE EVALUATIONS, COMPILED DATA, DUCTILITY, FUEL ELEMENT FAILURE, FUEL-CLADDING INTERACTIONS, LIMITING VALUES, LOSS OF COOLANT, MATERIALS TESTING, NSRR REACTOR, NUCLEAR FUELS, NUCLEAR POWER PLANTS, PWR TYPE REACTORS, QUENCHING, REACTOR OPERATION, REACTOR SAFETY, RISK ASSESSMENT, SAFETY MARGINS, THERMODYNAMIC PROPERTIES, ZIRCONIUM
ACCIDENTS, DATA, DEPOSITION, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EVALUATION, FAILURES, FUELS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, INFORMATION, MATERIALS, MECHANICAL PROPERTIES, METALS, MIXED SPECTRUM REACTORS, NUCLEAR FACILITIES, NUMERICAL DATA, OPERATION, PHYSICAL PROPERTIES, POOL TYPE REACTORS, POWER PLANTS, POWER REACTORS, PULSED REACTORS, REACTOR ACCIDENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SOLID HOMOGENEOUS REACTORS, SURFACE COATING, TENSILE PROPERTIES, TESTING, THERMAL POWER PLANTS, THERMAL REACTORS, TRANSITION ELEMENTS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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