有机工质反应堆燃料组件物理计算及堆芯设计  

Novel Organic Nuclear Reactor Fuel Assembly Physical Calculation and Reactor Core Design

作　　者：王锋[1,2] 孙源楠 苏兴康 WANG Feng;SUN Yuannan;SU Xingkang(School of Energy and Power Engineering,Chongqing University,Chongqing 400030,China;Key Laboratory of Low-grade Energy Utilization Technologies and Systems of Ministry of Education,Chongqing University,Chongqing 400030,China)

机构地区：[1]重庆大学能源与动力工程学院,重庆400030 [2]重庆大学低品位能源利用技术及系统教育部重点实验室,重庆400030

出　　处：《材料导报》2021年第18期18195-18199,共5页Materials Reports

基　　金：核反应堆系统设计技术重点实验室基金项目(JG2018119);重庆市技术创新与应用示范(产业类重点研发)基金项目(CSTC2018JSZX-CYZDX0100)。

摘　　要：有机工质堆芯因其特有的优势可用于移动核动力反应堆。本工作在以三联苯(C_(18)H_(14))为冷却剂和慢化剂的基础上,设计石墨慢化的有机工质反应堆(ONR)堆芯燃料组件,采用蒙特卡罗程序研究了石墨棒束对组件物理特性的影响,并分析了ONR组件的反应性控制特性。计算得到不同石墨棒数下ONR燃料组件中子能谱、每次裂变平均释放的能量、每次裂变释放的中子数、组件相对释放能量、k_(eff)、功率峰因子、冷却剂和石墨中能量沉积份额,以及可燃毒物和控制棒的微分价值。研究结果对ONR堆芯功率的设计和优化有一定的参考价值。Organic nuclear reactor core is advantageous for mobile nuclear power applications.In this study,based on the design of C_(18)H_(14)as both coolant and moderator,novel design of graphite moderated,C_(18)H_(14)cooled organic working medium reactor(ONR)core and fuel assembly was carried out.Monte Carlo code was used to study physical properties with different numbers of graphite rod,and fuel assembly control was also analyzed.Neutron characteristic results of neutron spectrum,energy release,the number of total neutrons per fission,percent energy deposition on the coolant and graphite under different numbers of graphite,k eff,and relative peak power were obtained.And the fuel assembly perfor-mance including differential value of burnable poison and control rod were also acquired.These results can be used as reference for the design of the ONR power and optimization.

关 键 词：有机工质反应堆 燃料组件 石墨慢化 蒙特卡罗方法 物理特性 

分 类 号：TL349[核科学技术—核技术及应用]