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Radiation hardening and IASCC susceptibility of extra high purity austenitic stainless steel

  • Published:2011-10 Issue:1-3 Volume:417 Page:887-891
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Ioka Ikuo,Ishijima Yasuhiro,Usami Kouji,Sakuraba Naotoshi,Kato Yoshiaki,Kiuchi Kiyoshi

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. A review of irradiation assisted stress corrosion cracking

2. Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

3. G.S. Garner, H.R. Brager, Effect of radiation on materials, in: 12th International Symposium of ASTM STP 870, Philadelphia, 1985, p. 187.

4. K. Kiuchi, I. Ioka, M. Takizawa, S. Wada, Technical committee meeting of IAEA, Argentina, Nov. 15–19, 1999.

5. J.P. Robertson, I. Ioka, A.F. Rowcliffe, M.L. Grossbeck, S. Jitsukawa, in: 18th International Symposium of ASTM STP 1325, Hyannis, 1999, p. 671.

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1. A Brief Review on He Ion Irradiation Research of Steel and Iron-Based Alloys in Nuclear Power Plants;Acta Metallurgica Sinica (English Letters);2022-10-25

2. Corrosion Characteristics of Candidate Alloys;Corrosion Characteristics, Mechanisms and Control Methods of Candidate Alloys in Sub- and Supercritical Water;2021-12-08

3. Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors;Journal of Alloys and Compounds;2021-07

4. Interaction Mechanism of Dislocation and Hydrogen in Austenitic 316 Stainless Steel;ACTA METALL SIN;2021

5. Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment;Corrosion Science;2020-09
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