Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding

被引：4
|
作者：
Hong, Jong-Dae [1 ]
Park, Myungchul [1 ]
Holston, Anna-Maria Alvarez [2 ]
Stjarnsater, Johan [2 ]
Kook, Donghak [1 ]
机构：
[1] Korea Atom Energy Res Inst, 989-111 Daedeok Daero, Daejeon 34057, South Korea
[2] Studsvik Nucl AB, S-61182 Nykoping, Sweden
来源：
JOURNAL OF NUCLEAR MATERIALS | 2021年 / 543卷
关键词：
DHC; Threshold stress intensity factor; PWR spent fuel; Dry storage; FUEL; HYDROGEN; TEMPERATURE;
D O I：
10.1016/j.jnucmat.2020.152596
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The delayed hydride cracking (DHC) is becoming important because of its extended long-term dry storage and lower dry storage temperature than expected. However, it remains difficult to predict the DHC behavior of PWR spent fuel cladding due to the limited data of K-IH (i.e., threshold stress intensity factor), especially for irradiated claddings. In this regard, the K IH for unirradiated and irradiated (49.641 GWd/tU) Zircaloy-4 claddings were experimentally measured using a pin-loaded-tension (PLT) technique and described by investigating the affected parameters. In addition, the results were compared with estimations from our previous studies. From the analysis, DHC is not expected to be a major concern during the predicted conditions of dry storage. (C) 2020 Elsevier B.V. All rights reserved.
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页数：8
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