The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior-Reference-Cited by-同舟云学术

The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior

Published:2009-05 Issue:1 Volume:389 Page:127-136
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Une K.,Ishimoto S.,Etoh Y.,Ito K.,Ogata K.,Baba T.,Kamimura K.,Kobayashi Y.

Publisher

Elsevier BV

Subject

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

Reference24 articles.

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3. Solubility of hydrogen in Zircaloy-4: irradiation induced increase and thermal recovery

4. H.M. Cheng, R.S. Daum, J.M. Hiller, M.C. Billone, Zirconium in the Nuclear Industry, in: Thirteenth International Symposium, ASTM STP 1423, 2002, p. 561.

5. K. Ogata, T. Baba, K. Kamimura, T. Kubo, K. Une, Y. Etoh, Paper Presented at Fifteenth International Symposium on Zirconium in the Nuclear Industry, Sunriver, USA, June 24–28, 2007.

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