Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference31 articles.
1. J. Buongiorno, P.E. MacDonald, Supercritical water reactor (SCWR): progress report for FY-0, INEEL, 2003.
2. Mechanism of irradiation assisted stress corrosion crack initiation in thermally sensitized 304 stainless steel
3. K. Fukuya, K. Fujii, Y. Kitsunai, Deformation Structure in 316 Stainless Steel Irradiated in a PWR, in: Proc. 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Salt Lake City, UT, 2005, p. 389.
4. A phenomenological investigation of in-reactor cracking of type 304 stainless steel control rod cladding
5. Contribution of Localized Deformation to IGSCC and IASCC;Was,2006
Cited by
41 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