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中国先进研究堆安全设计

Safety Design of China Advanced Research Reactor

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【作者】 刘天才杨长江刘兴民金华晋袁履正

【Author】 LIU Tian-cai YANG Chang-jiang LIU Xing-min JIN Hua-jin YUAN Lu-zheng(Department of Reactor Engineering Research & Design,China Institute of Atomic Energy,Beijing,102413,China)

【机构】 中国原子能科学研究院反应堆工程研究设计所中国原子能科学研究院反应堆工程研究设计所 北京102413北京

【摘要】 中国先进研究堆(CARR)是一座轻水冷却和慢化、重水反射的池内簟式研究堆。额定核功率为60MW。堆芯装载21盒燃料组件,芯体材料为U3Si2-Alx弥散体,包壳材料为6061铝。CARR具有堆芯小、热流密度高和流速高等特点,使得CARR的安全设计难度很大。本文详细介绍了CARK设计中采取的安全措施,如ATWS缓解系统、足够大的主泵转动惯量、足够的自然循环能力和靠UPS供电的随堆运行的应急堆芯冷却系统等。事故分析结果表明,CARR具有很高的固有安全性,采取的安全措施是有效的。

【Abstract】 China Advanced Research Reactor(CARR)is of tank-in-pool type,cooled and moderated by light water and reflected by heavy water.The rated nuclear power is 60 MW.It consists of 21 plate-type fuel assemblies.The fuel meat is made of U3Si2-ALx dispersion and the cladding is made.of 6061 aluminum alloys.The reactor has a small core with high heat flux and high coolant velocity.All these characteristics result in the difficulties in the safety design of CARR.Many measures have been taken in CARR design in order to assure the safety of the reactor.For instance,ATWS mitigation system,adequate main pump inertia, enough natural circulation ability,passive flapping valves for natural circulation and ECCS(Emergency Core Cooling System)supported by UPS are adopted at the same time.The accidents analysis results indicate that CARR is with high inherent safety and the safety measures are effective.

  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2006年S2期
  • 【分类号】TL411
  • 【被引频次】8
  • 【下载频次】252
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