首页|Effects of irradiation on the multi-field coupling delayed hydride cracking behavior of zirconium alloys

Effects of irradiation on the multi-field coupling delayed hydride cracking behavior of zirconium alloys

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  • NSTL
  • Elsevier
With high mechanical strength, good corrosion resistance and small thermal neutron absorption cross-section, zirconium based alloys are widely used as the nuclear structural materials. Stress concentra-tion usually appears in zirconium-based-alloy components during their reactor service phase or the stor-age stage of spent fuels, which could induce the delayed hydride cracking (DHC) behavior to seriously threaten the nuclear safety. In this study, an innovative multi-field coupling theoretical frame is devel -oped, with the effects of texture factor, with the irradiation hardening and embrittlement effects as well as the hydride orientation contributions involved in the cohesive model, with the hydrogen diffusion affected by the irradiation-induced variations of Nb concentration. The multi-field coupling simulation results indicate that (1) the predictions of the DHC velocities for different irradiation doses are in good agreement with the experimental data, and the subcritical cracking traits can be captured, which vali-dates the effectiveness of the newly developed models; (2) the irradiation-enhanced hydrogen diffusion coefficient plays a dominant role in the increase of DHC velocity with the radiation dose; (3) the irra-diation hardening leads to the increases of hydrostatic stress gradient and the concentration gradient of solid-soluted hydrogen atoms, which accelerates the diffusion flux of hydrogen atoms towards the crack tip region; (4) essentially, it is the irradiation hardening that shortens the required length of hydrided zone to initiate new fracture, and quicken the multi-coupling cracking process. This work lays a founda-tion for the further study of delayed hydride cracking behavior.(c) 2022 Elsevier B.V. All rights reserved.

Delayed hydride crackingMulti-field coupling crackingIrradiation hardening and embrittlementHydride orientationIrradiation-enhanced hydrogen diffusionCohesive zone modelSTRESS INTENSITY FACTORMECHANICAL-PROPERTIESFRACTURE-TOUGHNESSINDUCED EMBRITTLEMENTTEMPERATUREHYDROGENZIRCALOYMODELINITIATIONMICROSTRUCTURE

Chen, Liang、Ding, Guochen、Xia, Zhongjia、Zhang, Jingyu、Ding, Shurong、Pang, Hua、Song, Xiaoming

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Nucl Power Inst China

Fudan Univ

2022

10.1016/j.jnucmat.2022.153605

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.563
  • 8
  • 59