摘要
本文主要对4种FCM燃料-SiC包壳概念组件进行中子学分析评价,从安全性和经济性出发,一方面需要组件栅格首先满足欠慢化要求,保证堆芯慢化剂温度系数为负,确保堆芯固有安全性;二是经济性,FCM-SiC概念组件用于商用电站时,达到与参照对象基本相当的燃耗深度与循环长度。通过对比ORNL设计方案,提出TRISO核芯材料、颗粒体积份额、颗粒核芯直径、燃料富集等改进方向,然后进行了单因素影响分析和多因素组合影响分析,最后提出可以通过选取UN核芯、提高燃料富集度,增加燃料颗粒体积份额以及相对较大的核芯直径,使慢化剂温度系数和组件燃耗满足设计要求。
In this paper, neutronic evaluation has been taken on four kinds of FCM fuel SiC cladding conceptual assemblies. From the points of economy and security, neutronic evaluation is taken out to check whether the FCM fuel SiC cladding conceptual assemblies can meet the requirements of nuclear design. On one hand, the assembly grids should satisfy the over moderation requirement, so the moderator temperature coefficient of the core is negative to ensure the inherent safety of the core, on the other hand, when fuel SiC cladding conceptual design assemblies are used on commercial power plants, the burn up and cycle length should be nearly the same with the reference assemblies. By comparing with the assemblies of ORNL, the improving directions such as choosing high density TRISO kernel material, improving TRISO particle volume fraction, increasing kernel diameter of TRISO particle and improving fuel enrichment are proposed. And then single factor analysis and multi factor analysis are conducted, the final conclusion is that it’s possible to choose UN kernel, improve fuel enrichment, improve TRISO particle volume fraction, and improve kernel diameter to make the moderator temperature coefficient and cycle length meet the design requirements, and so the security and economy of the core can be guaranteed.
出处
《科技创新导报》
2018年第23期70-74,共5页
Science and Technology Innovation Herald
基金
四川省青年基金(项目编号:2016JQ0045)
