Fracture-mechanics-based evaluation of failure limit on pre-cracked and hydrided Zircaloy-4 cladding tube under biaxial stress states

被引:4
|
作者
Li, Feng [1 ]
Mihara, Takeshi [1 ]
Udagawa, Yutaka [1 ]
Amaya, Masaki [1 ]
机构
[1] Japan Atom Energy Agcy, Nucl Safety Res Ctr, 2-4 Shirakata, Tokai, Ibaraki 3191195, Japan
关键词
Reactivity-initiated accident; pellet-cladding mechanical interaction failure; Zircaloy-4; cladding; pre-crack; hydride; biaxial stress condition; J-integral; FUEL CLADDINGS; BEHAVIOR; TESTS;
D O I
10.1080/00223131.2019.1709996
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
To better understand the failure limit of fuel cladding during the pellet-cladding mechanical interaction (PCMI) phase of a reactivity-initiated accident (RIA), pre-cracked and hydrided cladding samples with base metal final heat-treatment status of cold worked (CW) and recrystallized (RX) were tested under biaxial stress conditions (strain ratios (epsilon(z)/epsilon(theta)) of 0 and 0.5). Displacement-controlled biaxial-expansion-due-to-compression (biaxial-EDC) tests were performed to obtain the hoop strain at failure (failure strain) of the samples. The conversion of the failure strains to J-integrals at failure (J(IC)) by finite-element analysis involving data of stress-relieved (SR) cladding specimens from our previous study revealed that the failure limit in the dimension of J(IC) unifies the effects of pre-crack depth. About 30-50% reduction in the J(IC) value was observed as the strain ratio increased from 0 to 0.5 irrespective of the annealing type, pre-crack depth, and hydrogen content. The rate of fractional decreases of J(IC) with increase of hydrogen content is in the order of CW>SR>RX, which are essentially independent of strain ratio for the CW and SR samples. The results were incorporated into the failure prediction model of the JAEA's fuel performance code in the form of a correction factor that considers the biaxial loading effect.
引用
收藏
页码:633 / 645
页数:13
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