The influence of testing conditions and irradiation on the stress corrosion cracking susceptibility of zircaloy-Reference-Cited by-同舟云学术

The influence of testing conditions and irradiation on the stress corrosion cracking susceptibility of zircaloy

Published:1980-11 Issue:1-2 Volume:95 Page:210-218
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lunde Liv,Videm Ketil

Publisher

Elsevier BV

Subject

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

Reference10 articles.

1. Proc. Conf. on Ramping and Load Following Behaviour of Reactor Fuel;Garlick,1978

2. Paper presented at IAEA Specialists' Meeting on Pellet Cladding Interaction for Water Reactors;Garzarolli,1977

3. EPRI-NASA Cooperative Project on Stress Corrosion Cracking of Zircaloys;Cubicciotti;EPRI-NN-717,1978

4. Paper presented at IAEA Specialists' Meeting on Power Ramping and Power Cycling of Water Reactor Fuel and Its Significance to Fuel Behaviour;Lunde,1979

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1. Direction to the Real Solution of SCC Initiation Mechanism;Journal of the Atomic Energy Society of Japan;2007

2. Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review;Journal of Nuclear Materials;1990-08

3. Influence of some factors on the susceptibility of Zircaloy-2 tubes to iodine stress corrosion cracking;Journal of Nuclear Materials;1989-05

4. Reactions and products in the Cs-Zr-I-O system relevant to fission product chemistry — a review;Journal of Nuclear Materials;1988-02

5. The influence of localized stresses and strains on the iodine scc behavior of Zircaloy-2 tubing;Journal of Nuclear Materials;1985-04