作者：郑兰疆, 王广金, 周天

作者单位：中国核动力研究设计院，四川 成都 610041

关键词：老化因素;导体组件;辐照寿命;热寿命

摘要：

电气贯穿件作为安装在核反应堆上的核安全级设备，国产化研发明确提出了60年的服务寿命要求。为此，该文通过研究核环境条件下设备的老化因素，得出电气贯穿件导体组件的辐照寿命和热寿命直接决定电气贯穿件的寿命。该文利用核反应堆孔道对导体组件进行在平均剂量率为0.88 Mrad/h条件下的总累积γ射线剂量100 Mrad的辐照试验，并进一步利用常规法进行导体组件的热寿命试验且获得试验方程，由此说明电气贯穿件能满足核电站60年的老化要求。与核行业传统的10 ℃定律以及保守活化能取值法相比，该文采用方法结合实际状态，可提升电气贯穿件老化寿命试验评估的准确性，在核行业老化寿命评估中具有较高的可参考性。

Research of aging life for feedthrough of electrical penetration assemblies in nuclear power plant
ZHENG Lanjiang, WANG Guangjin, ZHOU Tian
Nuclear Power Institute of China, Chengdu 610041, China
Abstract: Electrical penetration assemblies are nuclear-safety-level equipment installed on nuclear power plant. The 60-year service life requirement of electrical penetration assemblies is clearly stated in the domestic research and development. Based on the research on the aging factors of equipment under nuclear environmental conditions, we found that the radiation life and thermal life of the feedthrough directly determine the life of the electrical penetration assemblies. In this article, under the condition of an average dose rate of 0.88 Mrad/h and a total cumulative γ-ray dose of 100 Mrad, the feedthrough was irradiated using nuclear reactor tunnels. Furthermore, the test equation obtained from the thermal life test of the feedthrough by the conventional method can show that the electrical penetration assemblies can meet the 60-years aging requirements of nuclear power plants. Compared with the traditional 10 ℃ law and conservative activation energy value method in nuclear industry, the method adopted in this article is closely combined with the actual state, which improves the accuracy of aging life test evaluation of electrical penetration assemblies. Therefore, this method has a high reference value in the aging life assessment of nuclear industry.
Keywords: aging factors;feedthrough;irradiation life;thermal life
2021, 47(6):156-160  收稿日期: 2020-03-08;收到修改稿日期: 2020-07-09
基金项目:
作者简介: 郑兰疆(1982-),男,四川雅安市人,副研究员,硕士,研究方向为核反应堆设备研发
参考文献
[1] 陈金凤, 李忠诚, 董占发, 等. 百万千瓦级压水堆核电厂安全壳设计寿命60年结构分析评价[J]. 工业建筑, 2013, 43(S1): 156-160
[2] 郭宏恩. 核电汽轮机凝汽器运行参数动态特性仿真研究[J]. 中国测试, 2019, 45(8): 55-60
[3] CHAPIRO A, CLOUGH R, MERMILLIOD N, et al. What is ageing? Are there still problem to be solved[J]. Nuclear Instruments and Methods in Physics Research B, 1997, 131(1): x-xii
[4] CHIPARA M D, GRECU V V, CHIPARA M I, et al. On the radiation induced degradation of NBR-EPDM rubbers[J]. Nuclear Instruments and Methods in Physics Research B, 1999, 151: 444-448
[5] CLAVREUL R. Ageing of polymers in electrical equipment used in nuclear power plants[J]. Nuclear Instruments and Methods in Physics Research B, 1999, 151: 449-452
[6] PLACEK V, BARTONICEK B, HNAT V, et al. Dose rate effects in radiation degradation of polymer-based cable materials[J]. Nuclear Instruments and Methods in Physics Research B, 2003, 208: 448-453
[7] IEEE Standards Association. IEEE standard for electric penetration assemblies in containment structures for nuclear power generating stations:IEEE Std 317TM—2013[S]. USA: Nuclear Power Engineering Committee of the IEEE Power and Energy Society, 2013.
[8] 顾申杰. 核电厂1E级电气设备环境鉴定[J]. 核安全, 2005(2): 31-40
[9] 王福志, 姜松奕, 郑红, 等. 核电站用1E级电缆结构设计及有关试验的探讨[J]. 电线电缆, 2006(6): 14-18
[10] 孙建生, 陆燕红, 曲文波, 等. 核电站1E级电缆材料的辐照老化试验研究[J]. 电线电缆, 2010(1): 26-28
[11] 王海岭, 张红艳. 光伏电缆用绝缘及护套材料热老化寿命试验评定[J]. 光纤与电缆及其应用技术, 2017(2): 1-3
[12] IEEE Standards Association. IEEE Guide for the statistical analysis of thermal life test date：IEEE Std 101—1987(R2004)[S]. Statics Technical Committee of the IEEE Dielectrics and Electrical Insulation Society, 2004.
[13] 张攀, 那福利. 浅析在核安全设备质量鉴定过程中的热老化试验方法[J]. 核安全, 2015, 14(2): 68-74