基于RMC的NHR200-Ⅱ供热堆寿期分析  

Lifecycle Analysis of NHR200-Ⅱ Nuclear Heating Reactor Based on Reactor Monte Carlo Code

作　　者：李泽光[1] 郎明刚[1] 赵晶[1] 刘志宏[1] 王岩[1] 孙俊[1] LI Ze-guang;LANG Ming-gang;ZHAO Jing;LIU Zhi-hong;WANG Yan;SUN Jun(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《现代应用物理》2020年第1期76-81,共6页Modern Applied Physics

基　　金：国家自然科学基金资助项目(11775126,11545013)。

摘　　要：为深入研究NHR200-Ⅱ供热堆的寿期物理特性,采用国内自主研发的蒙特卡罗程序RMC对NHR200-Ⅱ反应堆进行了pin-by-pin精细建模,开展了全堆寿期计算与分析,计算了冷态零功率、热态零功率下的关键特性参数及考虑热工和临界棒位反馈下的热态满功率寿期燃耗,给出了keff及功率分布。结果表明,NHR200-Ⅱ供热堆具有较好的物理寿期特性,进一步验证了RMC程序在全堆精细模型寿期分析中应用的可行性。As a type of small module reactor(SMR),the nuclear heating reactor(NHR)has been researched and developed in the Institute of Nuclear and New Energy Technology(INET)of Tsinghua University,and a novel model of NHR200-Ⅱ is proposed.To obtain a better understanding of the reactor physical lifecycle characteristics of NHR200-Ⅱ,the first detailed Monte Carlo model of NHR200-Ⅱ including different types of complex fuel assemblies,cruciform control rods,and quarter core structures have been built by reactor Monte Carlo code(RMC).The key performance parameters of NHR200-Ⅱ are calculated under the cold zero power and the hot zero power,and the lifecycle fuel burnup under hot full power with considering the thermal and critical rod position feedback are also calculated.Then the keff and the power distributions of the NHR200-Ⅱ are given in detail.The results show that NHR200-Ⅱ heating reactor has better physical lifecycle characteristics,which further verifies the feasibility of RMC code in the lifecycle analysis of nuclear reactor full cores.

关 键 词：堆用蒙特卡罗程序(RMC) NHR200-Ⅱ 蒙特卡罗计算 寿期分析 

分 类 号：TM621.3[电气工程—电力系统及自动化]