Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5™ alloys in LOCA conditions

Laurence Portier, Thierry Bredel, Jean Christophe Brachet, Valerie Maillot, Jean Paul Mardon, Anne Lesbros, Michael Billone, Brian Cox, Arthur T. Motta

Research output: Chapter in Book/Report/Conference proceedingConference contribution

18 Scopus citations


The main objective of this paper is to describe the effects of a long service exposure of the PWR fuel cladding tubes on their thermal-mechanical properties during and after a hypothetical LOCA transient. Within this prospect, specific studies have been performed: on one hand, thermal ramp tests under uniaxial stress loading on as-received, pre-hydrided and irradiated samples of Zy-4 and M5™, and on the other hand, mechanical tests after high temperature oxidation and quench on as-received and prehydrided Zy-4 and MS™. The main conclusions are: (1) In service, hydrogen pick-up impacts the thermal ramp behavior under uniaxial stress loading of cladding tubes upon the first phase of LOCA transient, and the effect of the irradiation defects can be ignored for the conditions tested. (2) As-received Zy-4 and M5™ achieve comparable post-quench mechanical behavior at 1000, 1100, and 1200°C for representative times of LOCA transient (1800 s). (3) Oxygen has the most important effect in embrittlement of as-received Zr alloys at 1100 and 1200°C. (4) Hydriding has no effect on the oxidation kinetics at 1200°C, but after quenching the hydrided materials become brittle at a lower weight gain than as-received materials; this embrittlement is due both to an intrinsic hydrogen-embrittlement effect and to the oxygen content increase resulting from the effect of hydrogen on its solubility in prior-Beta phase.

Original languageEnglish (US)
Title of host publicationZirconium in the NUCLEAR INDUSTRY - Fourteenth International Symposium
PublisherAmerican Society for Testing and Materials
Number of pages25
ISBN (Print)0803134932, 9780803134935
StatePublished - 2005
Event14th International Symposium on Zirconium in the NUCLEAR INDUSTRY - Stockholm, Sweden
Duration: Jun 13 2004Jun 17 2004

Publication series

NameASTM Special Technical Publication
ISSN (Print)0066-0558


Other14th International Symposium on Zirconium in the NUCLEAR INDUSTRY

All Science Journal Classification (ASJC) codes

  • General Engineering


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