Author:
Yan Huan,Liu Xiang,He Lingfeng,Stubbins James
Funder
U.S. Department of Energy
Office of Nuclear Energy
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference40 articles.
1. Ferritic/martensitic steels for next-generation reactors;Klueh;J. Nucl. Mater.,2007
2. Low-activation ferritic and martensitic steels for fusion application;Kohyama;J. Nucl. Mater.,1996
3. 9 - Irradiation-resistant ferritic and martensitic steels as core materials for Generation IV nuclear reactors;Henry,2017
4. J. P. Wharry, Z. Jiao, V. Shankar, J. T. Busby, and G. S. Was, “Radiation-induced segregation and phase stability in ferritic–martensitic alloy T 91,” J. Nucl. Mater., vol. 417, no. 1, pp. 140–144, Oct. 2011, doi: 10.1016/j.jnucmat.2010.12.052.
5. Mechanical properties of modified 9Cr–1Mo (T91) irradiated at ⩽300 °C in SINQ Target-3;Dai;J. Nucl. Mater.,2003
Cited by
4 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