摘要
反应堆中各结构部件的抗辐照性能,对整个系统的使用寿命及安全性有较大的影响。本工作通过MCNPx2.70蒙特卡罗软件建立CiADS散裂靶次临界反应堆模型,结合NJOY2016核数据截面处理软件制作的材料原子离位截面,在堆芯组件数分别为30,42,72盒的情况下分别计算和分析了316L、15-15Ti、SIMP 3种不锈钢材料和ZTA陶瓷作为候选结构材料的中子辐照损伤情况。当用作CiADS燃料包壳时,3种不锈钢材料中SIMP制成的包壳的Rdpa值最小,在燃料组件数为30,42,72盒的情况下其年辐照损伤量分别约为1.16,1.61和12.0 dpa/a。而ZTA制成的燃料包壳的Rdpa值均大于不锈钢材料的辐照损伤。在散裂靶次临界反应堆耦合区域,轴向上CiADS中心管在束靶作用面附近所受到的辐照损伤最大。燃料组件数为30盒时,由316L制成的中心管的辐照损伤率峰值约为2.7 dpa/a。
The irradiation resistance capability of structural components in nuclear reactors has a great influence on the system's service life and safety.In this work,the CiADS coupling model between spallation target and subcritical reactor is established by MCNPx2.70,and the atomic dissociation cross sections for CiADS candidate materials are processed by the nuclear data processing software NJOY2016.The irradiation damages for three kinds of stainless steels,316L,15-15Ti,SIMP and one kind of ZTA ceramics are calculated and analyzed under three conditions with the number of fuel assemblies of 30,42 and 72,respectively.When used as CiADS fuel cladding,SIMP steel has the lowest rate of irradiation damage among the three candidate steels.The calculated irradiation damage rate are 1.16,1.61 and 12.0 dpa/a when the number of fuel assemblies are 30,42 and 72,respectively.The irradiation damage rate for the fuel cladding made of ZTA materials is much higher than that of the candidate steels.The CiADS center tube suffers the strongest neutron irradiation for the portion near the reaction area between the accelerator beam and the spallation target.The maximum irradiation damage rate is about 2.7 dpa/a for the center tube made of 316L steel when the fuel assemblies are 30.
作者
黄思洋
骆鹏
张璐
徐俊奎
黄郁旋
颜永刚
HUANG Siyang;LUO Peng;ZHANG Lu;XU Junkui;HUANG Yuxuan;YAN Yonggang(Institute of Modern Physics,Chinese Academy of Sciences,Lanzhou 730000,China;University of Chinese Academy of Sciences,Beijing 100049,China)
出处
《原子核物理评论》
CAS
CSCD
北大核心
2019年第4期484-491,共8页
Nuclear Physics Review
基金
国家自然科学基金资助项目(91426301)~~
