热管堆高温数据库的制作及堆芯初步物理计算  

Development of High-Temperature Nuclear Database and Preliminary Physical Computation of a Heat Pipe Reactor

作　　者：屈伸 曹良志[1] 郑琪 刘汉刚[2] 赵小林[2] 

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国工程物理研究院核物理与化学研究所,绵阳621900

出　　处：《现代应用物理》2017年第4期82-89,95,共9页Modern Applied Physics

摘　　要：利用核数据库处理程序NJOY,制作了1 700K和1 750K温度下,热管堆中45种核素的高温核数据库,并利用ICSBEP2006中的临界基准题对所制作的数据库加以验证。分别利用所制作的数据库和蒙特卡罗程序MCNP对堆芯进行了建模,计算了堆芯的有效增殖系数k_(eff),确定了热管堆中燃料的尺寸和富集度,分析了堆芯的相对功率分布。最后,初步计算了热管堆在水淹和沙埋2种事故工况下的k_(eff)以及安全棒价值,为堆芯安全分析和事故分析提供了基础参数。Based on the nuclear database processing code NJOY,a high temperature nuclear database containing 45 kinds of nuclides of the heat pipe reactor is developed at tempertures of 1 700 Kand 1 750 K,and it is verified by using some critical benchmarks of ICSBEP2006.The core of the heat pipe reactor is modeled by using Monte Carlo program MCNP,and the core geometry and the concentration of fuel are determined by calculating the effective multiplication factor k_(eff).Then,the relative power distributions of the core at different conditions are calculated and analyzed.Finally,the k_(eff)and the safety rod value under water logging and sand burial are preliminarily calculated for the safety and accident analysis of the core.

关 键 词：热管堆 核数据库 蒙特卡罗程序 有效增殖系数 安全棒价值 

分 类 号：TL329[核科学技术—核技术及应用]