PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY

doi:10.3724/SP.J.1037.2009.00868

Acta Metall Sin

2010, Vol. 46

Issue (7): 805-809 DOI: 10.3724/SP.J.1037.2009.00868

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PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY

SUN Chao¹⁾, TAN Jun²⁾, YING Shihao¹⁾, LI Cong³⁾, PENG Qian¹⁾, ZHAO Suqiong¹⁾

1) National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China, Chengdu 610041
2) Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900
3) Dept. of R$\&$D, State Nuclear Power Technology Corp., Ltd. Beijing 100140

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SUN Chao TAN Jun YING Shihao LI Cong PENG Qian ZHAO Suqiong. PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY. Acta Metall Sin, 2010, 46(7): 805-809.

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Abstract

Delayed hydride cracking (DHC) has been recognized as a potential threat to the structural integrity of zirconium alloy components in water-cooled nuclear reactors since the early 1970 s. Although DHC has been studied for a long time, most of the investigations were focused on unirradiated Zr-Nb and Zr-Sn alloys, no information was found on Zr-Sn-Nb alloy. Currently, several new Zr-based alloys have been developed from the point of view of enhancement of corrosion resistance and hydrogen pickup properties. In China, N18 (Zr-Sn-Nb) alloy has been developed based on Zr-Sn and Zr-Nb systems to meet the requirements of higher fuel burn-up. Therefore, it is necessary to investigate the DHC behavior of N18 alloy systematically. The objective of this study is to predict the critical temperatures for initiating and arresting DHC in irradiated N18 alloy. A model used to forecast DHC critical temperature of irradiated zirconium alloys was established based on the terminal solid solubility of hydrogen in irradiated zirconium alloys and stress-induced hydrogen diffusion. By using the model, the critical temperatures for irradiated N18 alloy were predicted. The result showed that the irradiated N18 alloy has high sensitivity for DHC initiation, because neutron irradiation increased the solubility of hydrogen and yield strength of N18 alloy. Compared with unirradiated N18 alloy, the critical temperature of irradiated N18 alloy rise nearly 20℃. The variation of critical temperatures of irradiated N18 alloy is similar to the unirradiated one. T_c is slightly less than T_h.

Key words: N18 zirconium alloy irradiation damage delayed hydride cracking (DHC) critical temperature

Received: 29 December 2009

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Supported by Foundation for Young Scholars of NPIC (No.JJXM-QNJJ-09-04-04)

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https://www.ams.org.cn/EN/10.3724/SP.J.1037.2009.00868 OR https://www.ams.org.cn/EN/Y2010/V46/I7/805

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