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多用途小型核反应堆电源热工水力设计分析

Reactor Core Design and Analysis for a Micro Nuclear Power Source

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【作者】 刘逍王成龙苏光辉秋穗正田文喜

【Author】 Xiao Liu;Chenglong Wang;Guanghui Su;Suizheng Qiu;Wenxi Tian;School of Nuclear Science and Technology, Xi’an Jiaotong University;

【机构】 西安交通大学核科学与技术学院

【摘要】 专为空间或水下航行器设计的微热管冷却反应堆电源(HRP)满足未来对能源系统更安全的结构,更长的运行时间,更少的机械运动部件的需求。本文提出了一种能够提供50kWe电功率的热管冷却反应堆电源系统。选用氮化铀作为燃料的,堆芯由37个钾高温热管冷却。屏蔽层采用钨和水联和轻质屏蔽材料,反应堆反应性由控制鼓控制。热电转换系统(TEG)由热电转换单元和水冷却器组成。热电转换单元通过高性能热电材料将热能转换成电能。开发了用于设计和分析热管冷却反应堆系统的程序。它由多通道堆芯模型,热管网模型,热电转换模型组成。通过程序对设计的小型核电源的两个关键参数冷凝段的长度(0.45m)和TEG的冷端温度(280K)进行灵敏度分析。同时还进行了稳态计算,包括位于反应堆堆芯中心的最高燃料温度938K,冷却剂的出口温度达到316K。结论是HPR设计合理可靠。设计的余热排出系统具有足够的安全裕度排出反应堆产生的裂变热,同时提供稳定的电能输出。

【Abstract】 Micro heat pipe cooled reactor power source(HRP) designed for space or underwater vehicles meets the future demands, such as safer structure, longer operating time, fewer mechanical moving parts. In this paper, potas-sium heat pipe cooled reactor power source system which generates 50 kWe electricity is proposed. The reactor core using Uranium nitride fuel is cooled by 37 potassium high temperature heat pipes. The shields are designed as Tungsten and water and reactor reactivity is controlled by control drums. The thermoelectric generator(TEG) consists of thermoelectric conversion units and water cooler. The thermoelectric conversion units convert thermal energy to electric energy through the high-performance thermoelectric material. A code applied for designing and analyzing the reactor power system is developed. It consists of multi-channel reactor core model, heat pipe model using thermal resistance network, thermoelectric conversion and thermal conductivity model. Then the sensitivity analysis is performed on two key parameters of the designed micro-nuclear power source. They are the length of the heat pipe condensation section 0.45 m and the cold junction temperature 280 K of TEG. Meanwhile the steady-state calculations are also conducted,including the maximum fuel temperature 938 K which is located in the center of reactor core and the outlet temperature of coolant reaching 316 K. It is concluded that the preliminary design of HPR design is reasonable and reliable. The designed residual heat removal system has sufficient safety margin to release the decay heat of the reactor. This research provides valuable analysis for the application of micro nuclear power source.

  • 【会议录名称】 第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集
  • 【会议名称】第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会
  • 【会议时间】2019-11-06
  • 【会议地点】中国广东惠州
  • 【分类号】TL33;TM918
  • 【主办单位】中国核学会核能动力分会反应堆热工流体专业委员会、中核核反应堆热工水力技术重点实验室、核反应堆热工流体青年工作委员会
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