期刊文献+

熔融锆铁金属层顶部注水试验设计及结果

Experimental Design and Result of Water Injectionon Molten Zirconium-stainless Steel Metallic Pool
下载PDF
导出
摘要 通过向压力容器内注水的措施带走部分衰变热被认为是更高功率堆设计中缓解金属层“热聚焦”效应的潜在措施之一。但往金属层顶部注水可能存在复杂的物理现象,有必要开展试验研究,以验证该措施的可行性和有效性。本文以锆铁原型金属材料为工质,对金属层注水试验装置进行设计,并开展典型试验研究,对试验后的结果进行分析。研究结果表明:在本试验条件范围内,向金属层顶部注水未导致蒸汽爆炸、大量熔融物飞溅及氢气爆炸等现象,注水后金属层表面移出的热流密度高于实际电站下封头形成稳定熔池后向上的辐射换热热流密度。本文结果证明了通过向熔池顶部注水,有助于缓解金属层的“热聚焦”效应,可为严重事故下管理策略的制定提供有益指导。 Water injection on molten zirconium-stainless steel metallic pool to partly remove decay heat is regarded as one of potential strategies to mitigate the“heat focus”effect of metal layer for larger power reactors.But complicated phenomena may appear when water injection on the molten metallic pool,it’s necessary to perform experiments to investigate this strategies to verify its feasibility and effectiveness.The innovative design of the experimental system named ATOM(wATer injectiOn on molten zirconium-stainless steel Metallic pool experiment)was introduced in this paper.The prototype metallic material of zirconium and stainless steel were used for the working medium in this experimental facility.Based on the built experimental facility,experimental researches were conducted.The effects of different mass fractions of zirconium,water injection flow rates,and water subcooling(or water temperature)were considered in the setting of experimental conditions.The typical mass fractions of zirconium were 13%and 60%,the typical water injection flow rates were 0.05 kg/s and 0.10 kg/s,and the typical water subcooling were 15℃and 50℃.Nine experiments were conducted,and the results indicate that:1)This experimental facility design can successfully achieve the bottom heating and melting of the zirconium iron metal that is close to the prototype,and maintain the bottom heating state during water injection;2)The heat flux range of the molten metal layer surface with water injection is about 0.8-1.4 MW/m^(2) under the setting conditions of this experiment;3)The higher of the heat flux will achieve on the molten metal layer surface during water injection,with the larger of the water injection flow rate and the lower of the mass fraction of zirconium;4)Water injection on molten zirconium-stainless steel metallic pool does not cause phenomena such as steam explosion,splashing of a large amount of molten material,or hydrogen explosion under the conditions of this experiment.It can be concluded that the heat flux removed from the surface of metal layer after water injection is higher than the upward radiation heat flux density when the stable molten pool is formed in the actual lower head of the power plant.Water injection on molten zirconium-stainless steel metallic pool can help alleviate the heat focusing effect of the metal layer.The results of this research can provide valuable reference for severe accident mitigation strategy.
作者 房芳芳 韩昆 李宗洋 王增辉 FANG Fangfang;HAN Kun;LI Zongyang;WANG Zenghui(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China;State Power Investment Corporation Research Institute,Beijing 102209,China;Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China;Nuclear Industry Engineering Research and Design Co.,Ltd.,Beijing 101300,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第6期1327-1334,共8页 Atomic Energy Science and Technology
基金 国家科技重大专项(2018ZX06002-004)。
关键词 堆内注水 金属层顶部注水 堆内滞留 严重事故缓解 in-vessel water injection water injection on metallic pool in-vessel retention severe acci-dent mitigation
  • 相关文献

参考文献1

二级参考文献6

  • 1UK AP1000 probabilistic risk assessment report, UKP-GW-GL 022[R]. UK: Westinghouse Electric Corporation, 2007.
  • 2REMPE J L, KNUDSON D L, ALLISON C M, et al. Potential for AP600 in-vessel retention through ex-vessel flooding, INEEL/EXT-9700779[R]. US: OSTI, 1997.
  • 3SALTELLI A, CHAN K, SCOTT E M. Sensitivity analysis[M]. New York~ Wiley, 2000.
  • 4傅孝良,杨燕华,周卫华.CPRloOO堆大LOCA事故堆芯熔融及熔池传热特性分析[C]//2009年核动力厂严重事故管理研讨会.深圳:中科华核电技术研究院,2009.
  • 5TANG Boxin. Selecting Latin hypercubes using correlation criteria[J]. Statistica Sinica, 1998, 8 : 965-977.
  • 6Analysis of in-vessel retention and e~vessel fuel coolant interaction for AP1000, NUREG/CR6849, ERI/NRC-04-201[R].[S. 1.]: NR Energy Research, Inc. , 2004.

共引文献6

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部