Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage

被引：3

作者：

Hong, Jong-Dae ^{[1
]}

Yang, Yong-Sik ^{[1
]}

Kook, Donghak ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, ATF Technol Dev Div, 989-111 Daedeok Daero, Daejeon 34057, South Korea

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2020年 / 52卷 / 03期

关键词：

DHC; PWR spent fuel; dry storage; Sensitivity; BEHAVIOR;

D O I：

10.1016/j.net.2019.07.036

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：

In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (K-IH) was performed. However, there were a few limitations in the analysis of the cladding properties, such as oxide thickness and mechanical properties. In this study, those models were modified to include test data for irradiated materials, and the cladding creep model was introduced to improve the reliability of the DHC assessment. In this study, DHC susceptibility of PWR spent fuel during dry storage depending on the axial elevation was evaluated with the improved assessment methodology. In addition, the sensitivity of affecting parameters such as fuel burnup, hydride thickness, and crack aspect ratio are presented. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.

引用

页码：614 / 620

页数：7

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