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Accident analysis of heat pipe cooled space reactor

  • Yuan Yuan
  • , Jianqiang Shan
  • , Bin Zhang
  • , Junli Gou
  • , Bo Zhang
  • Xi'an Jiaotong University

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

A space power with high power density, light weight, low cost and high reliability is of crucial importance to future exploration of deep space. Space reactor is an excellent candidate because of its unique characteristics of high specific power, low cost, strong environment adaptability and so on. Among all types of space reactors, heat pipe cooled space reactor, which adopts the passive heat pipe as core cooling component, is considered as one of the most promising choice and is widely studied all over the world. A transient analysis code (TAPIRS) for heat pipe cooled space reactor power system is developed. The TAPIRS based on point reactor kinetics model, lumped parameter core heat transfer model, combined heat pipe (HP) model (self-diffusion model, flat-front startup model and network model), energy conversion model of alkali metal thermal-to-electric conversion units (AMTEC). and HP radiator model. Three typical accidents, i.e., control drum failure, AMTEC failure and partial loss of the heat transfer area of radiator arc then analyzed using TAPIRS. The results show that the heat pipe cooled space reactor has excellent inherent safety characteristics.

源语言英语
主期刊名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版商American Nuclear Society
4961-4971
页数11
ISBN(电子版)9781510811843
出版状态已出版 - 2015
活动16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, 美国
期限: 30 8月 20154 9月 2015

出版系列

姓名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
6

会议

会议16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国家/地区美国
Chicago
时期30/08/154/09/15

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