Author:
Miura Terumitsu,Fujii Katsuhiko,Fukuya Koji
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference29 articles.
1. Current understanding of radiation-induced degradation in light water reactor structural materials
2. Fracture behavior of austenitic stainless steels irradiated in PWR
3. K. Fujimoto, T. Yonezawa, E. Wachi, Y. Yamaguchi, M. Nakano, R.P. Shogan, J.P. Massoud, T.R. Mager, Effect of the accelerate irradiation and hydrogen/helium gas on IASCC characteristics for highly irradiated austenitic stainless steels, in: 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Salt Lake City, UT, USA, 2005, pp. 299–310.
4. Micromechanics of dislocation channeling in intergranular stress corrosion crack nucleation
5. Helium in fusion materials: High temperature embrittlement
Cited by
48 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献