Published 1999
| Version v1
Book
A BNR model for LWR fuel rod clad creep behaviour
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
Description
Semi-theoretical model was developed for predicting creep strain under thermal out-of-pile and in-pile conditions of interest for LWR type fuel rods. The results of model calculations were compared with an isothermal experiment data and post-irradiation examinations as available. Discussion was also given to the difference in creep behaviour between irradiated and unirradiated fuel cladding, indicating that model equations are applicable for predicting creep strain of spent fuel claddings. Strain-hardening and fluence/time-hardening effects were modelled and discussed. (authors)
Additional details
Additional titles
- Original title (English)
- Le combustible nucleaire des reacteurs a eau ordinaire a l'aube du troisieme millenaire
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- LWR nuclear fuel highlights at the beginning of the third millennium
- Imprint Pagination
- 584 p.
- Journal Page Range
- p. 332-346
Conference
- Title
- TopFuel'99. Proceedings of the SFEN/ENS conference
- Acronym
- International topical meeting
- Dates
- 13-15 Sep 1999
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 32000645
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; CREEP; F CODES; FAST NEUTRONS; FUEL RODS; IRRADIATION; STRAIN HARDENING; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; BARYONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; COMPUTER CODES; CORROSION RESISTANT ALLOYS; DEPOSITION; ELEMENTARY PARTICLES; FERMIONS; FUEL ELEMENTS; HADRONS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NEUTRONS; NUCLEONS; REACTOR COMPONENTS; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 19 refs. Imprint:Le combustible nucleaire des reacteurs a eau ordinaire a l'aube du troisieme millenaire