Author:
Zhao Wanqian,Wei Tianguo,Liao JingJing,Song Pengcheng,Peng Xiaoming,Liao Zhihai,Peng Qian,He Xueyi
Funder
National Natural Science Foundation of China
Subject
Materials Chemistry,Metals and Alloys,Mechanical Engineering,Mechanics of Materials
Reference29 articles.
1. Advanced treatment of Zircaloy cladding high-temperature oxidation in severe accident code calculations: Part I. Experimental database and basic modeling;Schanz;Nucl. Eng. Des.,2004
2. G. Hache, H.M. Chung, The History of LOCA Embrittlement Criteria, NUREG/CP-0172, 2001, pp. 205–237.
3. P. Hofmann, C. Politis, Chemical interaction between uranium oxide and zircaloy-4 in the temperature range between 900 and 1500 °C, in: Proceedings of the Fourth Conference on Zirconium in the Nuclear Industry, West Conshohocken, 197, 1979, pp. 537–560.
4. D.O. Hobson, P.L. Rittenhouse, Embrittlement of Zircaloy-Clad Fuel Rods by Steam during LOCA Transients, ORNL-4758, 1972.
5. Y. Yan, R.V. Strain, M.C. Billone, LOCA Research Results for High-Burnup BWR Fuel, NUREG/CP-0180, 2003, pp. 127–155.
Cited by
16 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