基于RMC的超临界水实验SCWR-FQT装置的初步物理分析  

Physical Analysis of SCWR-FQT Facility Based on RMC

作　　者：范潇[1,2] 王侃[2] 李泽光[2] 张国辉[1] 

机构地区：[1]北京大学物理学院,北京100871 [2]清华大学工程物理系,北京100084

出　　处：《原子能科学技术》2013年第B12期557-561,共5页Atomic Energy Science and Technology

基　　金：核能开发科研项目资助;国家自然科学基金资助项目(11175005);国家重点基础研究发展计划资助项目(2007CB209807)

摘　　要：中国和欧盟合作研究项目超临界水堆鉴定实验(Supercritical Water Reactor-Fuel Qualification Test,SCWR-FQT)的主要目的是研究水在超临界条件下对回路结构设计的影响,为研究设计超临界水堆做基础工作。本次研究对象为位于LVR-15实验堆堆芯中的超临界水实验SCWR-FQT装置。热工水力分析和回路设计的前提是堆芯及实验装置的物理分析,包括临界分析和燃耗分析等。RMC是清华大学自主研发的堆用蒙特卡罗分析软件,本文基于此软件对LVR-15堆芯和超临界实验装置进行了物理分析,并完成了全堆临界计算,得到了临界富集度、全堆芯中子通量分布和超临界装置中的中子能谱和通量分布,最后完成了全堆及超临界装置的燃耗计算和分析。Under the China-EU corporation project Supercritical Water Reactor-Fuel Qualification Test （SCWR-FQT）, a configuration of the LVR-15 core with the SCWR-FQT facility was constructed to study the impact of supercritical water on the loops designing. The neutron physical analysis of the core and facility is the premise of thermal analysis and designing of the loops. RMC code which was developed by Department of Engineering Physics, Tsinghua University as a tool for reactor physical analysis was used to analyze the LVR-15 core and SCWR-FQT facility. Criticality calculating was performed, and the fuel enrichment, whole core neutron flux distribution and neutron spectrum and neutron flux of the supercritical facility were obtained, based on which the burnup calculation and analysis of the core and FQT facility were completed.

关 键 词：超临界实验装置 临界计算 燃耗计算 RMC LVR 15 

分 类 号：TL326[核科学技术—核技术及应用]