Published 1999 | Version v1
Book

A BNR model for LWR fuel rod clad creep behaviour

  • 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)

Part of:
LWR nuclear fuel highlights at the beginning of the third millennium

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)

Optional Information

Notes
19 refs. Imprint:Le combustible nucleaire des reacteurs a eau ordinaire a l'aube du troisieme millenaire