Hydrogen analysis and slow strain rate test in Ar gas for irradiated austenitic stainless steel

Author:

Morisawa J,Kodama M,Yokota N,Nakata K,Fukuya K,Shima S,Asano K

Publisher

Elsevier BV

Subject

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

Reference22 articles.

1. M. Kodama, R. Katsura, J. Morisawa, S. Nishimura, S. Suzuki, K. Asano, K. Fukuya, K. Nakata, in: Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, San Diego, CA, August 1993, p. 583

2. H.M. Chung, W.E. Ruther, J.E. Sanecki, T.F. Kassner, in: Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, San Diego, CA, August 1993, p. 511

3. M. Kodama, S. Nishimura, J. Morisawa, S. Shima, S. Suzuki, M. Yamamoto, in: Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Monterey, CA, August 1991, p. 948

4. P.L. Andresen, F.P. Ford, S.M. Murphy, J.M. Parks, in: Proceedings of the Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Jekyll Island, GA, August 1989, p. 83

5. W.L. Clarke, A.J. Jacobs, in: Proceedings of the First International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Myrtle Beach, SC, August 1983, p. 451

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