Atomic Energy Science and Technology ›› 2018, Vol. 52 ›› Issue (7): 1186-1193.DOI: 10.7538/yzk.2018.52.07.1186

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Application of Evaluated Nuclear Data in Design of Heat Pipe Cooled Space Reactor

LI Songyang;WANG Dingqu;JIANG Yueyuan;LI Weihua;GUO Wenli   

  1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, China
  • Online:2018-07-20 Published:2018-07-20

评价核数据在热管冷却空间核反应堆设计中的应用

李松阳;王鼎渠;蒋跃元;李卫华;郭文利   

  1. 清华大学 核能与新能源技术研究院,先进核能技术协同创新中心,北京100084

Abstract:

Heat pipe cooled space reactor is an important candidate for space reactor power system. The materials applied in space reactor core are quite different to those in PWR core. Taking HP-SMTCs reactor core as an example, materials containing rhenium, molybdenum, lithium and beryllium are widely used. In order to examine the influence of evaluated nuclear data of these isotopes to the nuclear design of heat pipe cooled space reactor, Monte Carlo criticality calculations were done using cross section data from various sources and versions for HP-SMTCs core in different configurations. Neutron data files from ENDF/B series, JEFF and CENDL for rhenium and molybdenum which can stand high temperature environment were discussed. The Monte Carlo calculation results were compared. Sensitivity coefficients were calculated for main isotopes in the core, and finally the demand for evaluated nuclear data in space reactor area was pointed out.

Key words: evaluated nuclear data, space reactor, heat pipe, nuclear design

摘要:

热管冷却反应堆是空间核反应堆电源系统的重要候选堆型,具有良好的发展前景。热管冷却空间堆堆芯使用的材料与传统压水堆相比有很大不同,以HP-SMTCs堆芯为例,广泛使用了含有Re、Mo、Li、Be等元素的材料。为研究相应的评价核截面数据对热管冷却空间堆核设计产生的影响,以HP-SMTCs空间堆核设计为平台,选用不同来源、不同版本的评价核数据,对堆芯在不同构型下的临界安全进行了计算,对Re、Mo等耐高温材料的中子截面数据对空间堆核设计结果的影响进行了评价,比较了使用ENDF/B、JEFF、CENDL等常用评价库的核数据时的计算结果,对主要核素的截面数据进行了敏感性系数计算,并分析指出了未来空间堆发展对相关评价核数据的需求。

关键词: 评价核数据, 空间堆, 热管, 核设计