首页|Hydrogen solubility in Zr-Nb alloys

Hydrogen solubility in Zr-Nb alloys

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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.

Hydrogen trappingHydrogen embrittlementRadiation effectsZirconium alloysDFTZIRCONIUM ALLOYSCORROSION BEHAVIORHYDROGEN EMBRITTLEMENTINTERSTITIAL HYDROGENMECHANICAL-PROPERTIESPHASEMICROSTRUCTUREOXIDATIONNIDEGRADATION

Tuli, Vidur、Claisse, Antoine、Burr, Patrick A.

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Univ New South Wales

Westinghouse Elect Sweden

2022

Scripta materialia

Scripta materialia

EISCI
ISSN:1359-6462
年,卷(期):2022.214
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