Microstructural examination of high temperature creep failure of Zircaloy-2 cladding in irradiated PHWR fuel pins-Reference-Cited by-同舟云学术

Microstructural examination of high temperature creep failure of Zircaloy-2 cladding in irradiated PHWR fuel pins

Published:2012-10 Issue:1-3 Volume:429 Page:257-262
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Mishra Prerna,Sah D.N.,Kumar Sunil,Anantharaman S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference16 articles.

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3. Diameter increase in SGHWR cans under LOCA conditions, Zirconium in Nuclear Industry;Rose;ASTM STP,1977

4. H.E.Rosinger, H.J. Neitzel, F.J. Erbacher, The development of a burst criterion for Zircaloy cladding under LOCA condition, in: Proc. IAEA Specialist Meeting on Fuel Element Performance Computer Modelling, Blackpool, UK, March 17–21 1980, pp. 21–35.

5. Steady-state creep of zircaloy-4 fuel cladding from 940 to 1873 K

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