Hydrogen solubility in Zr-Nb alloys

被引:12
作者
Tuli, Vidur [1 ]
Claisse, Antoine [2 ]
Burr, Patrick A. [1 ]
机构
[1] Univ New South Wales, Sch Mech & Mfg Engn, Sydney, NSW, Australia
[2] Westinghouse Elect Sweden AB, S-72163 Vasteras, Sweden
关键词
Hydrogen trapping; Hydrogen embrittlement; Radiation effects; Zirconium alloys; DFT; ZIRCONIUM ALLOYS; CORROSION BEHAVIOR; INTERSTITIAL HYDROGEN; MECHANICAL-PROPERTIES; PHASE; MICROSTRUCTURE; OXIDATION; NI; EMBRITTLEMENT; DEGRADATION;
D O I
10.1016/j.scriptamat.2022.114652
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
We present a fast and accurate method for predicting the thermodynamics of hydrogen solubility and trapping in alloys, which is two orders of magnitude faster than conventional ab-initio approaches. The model hinges on the finding that the solubility of H is dominated by its nearest neighbour environment. We apply the method to the problem of hydrogen redistribution in Nb-containing Zr nuclear fuel cladding, and validated it against brute-force ab-initio approaches. We find that hydrogen preferentially dissolves into the beta-Zr phase found in as-manufactured 2.5%Nb alloys, and H is likely to redistribute into the a phase following the irradiation-induced decomposition of beta-Zr. beta-Nb particles found in as-manufactured 1%Nb alloys may act as weak sinks for H, however irradiation-induced change of composition of beta-Nb particles increases their hydrogen-trapping strength. Nano-platelets formed under irradiation in these alloys are potentially even stronger hydrogen sinks, especially if induced by proton irradiation rather than neutrons.
引用
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页数:6
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