PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY
Received date: 2009-12-29
Revised date: 2010-03-31
Online published: 2010-07-11
Supported by
Supported by Foundation for Young Scholars of NPIC (No.JJXM-QNJJ-09-04-04)
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. Tc is slightly less than Th.
XUN Tiao , TAN Jun , YING Shi-Gao , PENG Qian , LI Cong , DIAO Su-Qiong . PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY[J]. Acta Metall Sin, 2010 , 46(7) : 805 -809 . DOI: 10.3724/SP.J.1037.2009.00868
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