新型锆合金包壳材料商业反应堆辐照考验方案设计  

Irradiation Plan in Commercial Reactor for New Zirconium Alloy Cladding

作　　者：付浩 林少芳 洪志强 林煜宇 张利斌 聂立红 邓勇军 FU Hao;LIN Shaofang;HONG Zhiqiang;LIN Yuyu;ZHANG Libin;NIE Lihong;DENG Yongjun(Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing 102401,China;China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen 518000,China;Daya Bay Nuclear Power Operations and Management Co.,Ltd.,Shenzhen 518000,China)

机构地区：[1]生态环境部核与辐射安全中心,北京102401 [2]中广核研究院有限公司,广东深圳518000 [3]大亚湾核电运营管理有限责任公司,广东深圳518000

出　　处：《原子能科学技术》2021年第12期2346-2350,共5页Atomic Energy Science and Technology

摘　　要：对于一种新型锆合金包壳材料,在商业反应堆中开展服役条件下的辐照考验是其研发必不可少的关键环节。相比于国际核电发达国家在锆合金包壳材料研发中积累的丰富商业堆辐照考验,国内自主锆合金仅开展了有限的商业堆先导辐照考验,且考验的燃耗水平偏低。本文将通过对国外锆合金辐照考验经验的总结及自身实践经验,给出锆合金包壳商业反应堆辐照考验时在方案设计上的一般方法和堆芯安全评估、风险应对上的基本考虑,为国内锆合金商业堆辐照考验研究提供参考。For a new zirconium alloy cladding material, the irradiation in commercial reactor which is subject to test the in-pile performance, is an essential step in its development. Compared to the foreign zirconium alloy with rich irradiation experiences, the zirconium alloy independently developed in China has a limited number of irradiations with a relatively low burnup level. Based on the feedback from abroad experience and domestic practice in commercial reactor irradiation, some basic ideas and viewpoints were provided in plan design, safety evaluation and risk management in the paper. The results can offer a useful reference for the irradiation of domestic zirconium alloy in commercial reactor.

关 键 词：锆合金 包壳 辐照考验 

分 类 号：TL329.2[核科学技术—核技术及应用]