秦山二期堆芯临界计算中核数据的敏感性分析  

Sensitivity analysis of nuclear data in core critical calculation of Qinshan Ⅱ

作　　者：强胜龙 尹强[1] 芦韡[1] 李庆[1] 柴晓明[1] Qiang Shenglong Yin Qiang Lu Wei Li Qing Chai Xiaoming(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《强激光与粒子束》2017年第3期18-22,共5页High Power Laser and Particle Beams

基　　金：国家自然科学基金项目(11505175)

摘　　要：核电软件需要给出计算结果的不确定性,在此基础上才可有效评价核电的安全性。核数据是核电软件堆芯计算不确定性的重要来源之一,而堆芯宏观参数对核数据的敏感性分析是不确定性分析的重要步骤。以秦山二期堆芯为研究对象,对其临界计算结果开展核数据的敏感性分析。首先采用蒙特卡罗程序建立秦山二期首循环计算模型,然后基于中国核数据中心研制的连续能量截面库CENACE V1.0,采用反复裂变几率法计算有效增殖系数对核数据的敏感性系数。通过整理分析秦山二期冷热态、寿期初中末状态的敏感性系数,梳理出核电软件不确定分析中需要关注的重要核素数据。Nuclear power software needs to give the uncertainty of calculation results, thus it can effectively evaluate the safety of nuclear power. Nuclear data are important sources of uncertainty in core calculation, and the sensitivity analysis is an im- portant step for the uncertainty analysis of core parameter. The sensitivity analysis of nuclear data is carried out on the critical cal- culation in Qinshan Ⅱ core. Firstly, Monte Carlo procedures are used for the establishment of Qinshan Ⅱ＇s first cycle model, then the sensitivity coefficient of nuclear data is calculated with Iterated Fission Probability method（IFP） based on continuous en- ergy cross section library CENACE V1.0 developed by Chinese nuclear data center. By the analysis of the sensitivity coefficient with different temperature and different burnup, the important nuclear data to be concerned in the uncertainty analysis of nuclear power software would be found.

关 键 词：敏感性分析 截面 有效增殖因子 核电软件 堆芯 

分 类 号：TL329[核科学技术—核技术及应用]