French investigations of high burnup effect on LOCA thermomechanical behavior: Part 1. Experimental programmes in support of LOCA design methodologies
- 1. EDF/SEPTEN Villeurbanne (France)
- 2. IPSN, Cadarache (France)
- 3. EDF/SCMI, Chinon (France)
Description
Within the framework of Burn-Up extension request, EDF, FRAMATOME, CEA and IPSN have carried out experimental programmes in order to provide the design of fuel rods under LOCA conditions with relevant data. The design methods used in France for LOCA are based on standard Appendix K methodology updated to take into account some penalties related to the actual conditions of the Nuclear Power Plant. Best-Estimate assessments are used as well. Experimental programmes concern plastic deformation and burst behavior of advanced claddings (EDGAR) and thermal shock quenching behavior of highly irradiated claddings (TAGCIR). The former reveals the important role played by the α/β transformation kinetics related to advanced alloys (Niobium alloys) and the latter the significative impact of hydrogen charged during in-reactor corrosion on oxidation kinetics and failure behavior in terms of cooling rates
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging
- Imprint Pagination
- 372 p.
- Journal Page Range
- p. 151-160.
- Report number
- NUREG/CP--0157-Vol.1
Conference
- Title
- 24. water reactor safety information meeting.
- Dates
- 21-23 Oct 1996.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28068515
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FAILURE MODE ANALYSIS; FUEL CANS; HYDROGEN EMBRITTLEMENT; LOSS OF COOLANT; PHASE TRANSFORMATIONS; PLASTICITY; THERMAL SHOCK; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; EMBRITTLEMENT; MECHANICAL PROPERTIES; REACTOR ACCIDENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-9610202--Vol.1.