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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding
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Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding

机译:辐照和未照射锆型锆型渗透液裂解的阈值应力强度因子

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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.
机译:延迟氢化物裂解(DHC)由于其长期的干燥储存和低于预期的干燥储存温度而变得重要。然而,由于K-IH(即阈值应力强度因子)的有限数据,尤其是辐照包壳的数据,仍然难以预测压水堆乏燃料包壳的DHC行为。在这方面,使用销加载张力(PLT)技术对未辐照和辐照(49.641 GWd/tU)锆合金-4包层的K IH进行了实验测量,并通过研究受影响的参数进行了描述。此外,将结果与我们之前研究的估计值进行了比较。从分析结果来看,在预测的干燥储存条件下,DHC预计不会成为主要问题。(C) 2020爱思唯尔B.V.版权所有。

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