Dynamic strain aging behavior of accident tolerance fuel cladding FeCrAl-based alloy for advanced nuclear energy
Dynamic strain aging behavior of accident tolerance fuel cladding FeCrAl-based alloy for advanced nuclear energy
复制标题
先进核能耐事故燃料包壳FeCrAl基合金的动态应变时效行为
DOI:
10.1007/s10853-021-05820-6
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发表时间:
2021-02
影响因子:
4.5
通讯作者:
Wang Yuan
中科院分区:
文献类型:
--
作者:
Zhang Yiyong;Wang Hui;An Xuguang;Chen Guang;Sun Hongying;Wang Yuan
The Fe-13Cr-4Al alloy has become a promising candidate material for accident tolerance fuel (ATF) cladding of light-water reactors (LWRs) due to its excellent oxidation resistance to high-temperature water vapor. However, the tensile deformation behavior
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影响因子:
3.1
作者:
Ott, L. J.;Robb, K. R.;Wang, D.
通讯作者:
Wang, D.
影响因子:
3.1
作者:
Pint, B. A.;Terrani, K. A.;Keiser, J. R.
通讯作者:
Keiser, J. R.
影响因子:
9.4
作者:
Z. Sun;P. Edmondson;Y. Yamamoto
通讯作者:
Z. Sun;P. Edmondson;Y. Yamamoto
DOI:
10.1007/s11661-015-3000-7
发表时间:
2015-06
期刊:
Metallurgical and Materials Transactions A
影响因子:
--
作者:
G. Han;C. Tian;Z. Chu;C. Cui;Z. Hu;X. Sun
通讯作者:
G. Han;C. Tian;Z. Chu;C. Cui;Z. Hu;X. Sun
影响因子:
6
作者:
Edmondson, P. D.;Briggs, S. A.;Field, K. G.
通讯作者:
Field, K. G.