HTR-PM进气事故氧化分析

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英文篇名：Oxidation Analysis of the Air Ingress Accident for HTR-PM 作者：徐伟 ; 李云龙 ; 石磊 英文作者：XU Wei;LI Yunlong;SHI Lei;China Nuclear Power Engineering Co.,Ltd.Zhengzhou Branch;Institute of Nuclear and New Energy Technology,Tsinghua University; 关键词：HTR-PM ; 热气导管双端断裂 ; 燃料最高温度 ; 石墨氧化 英文关键词：HTR-PM;;DEGB of horizontal gas duct;;Maximum fuel temperature;;Graphite oxidation 中文刊名：HKXY 英文刊名：Nuclear Science and Engineering 机构：中国核电工程有限公司郑州分公司;清华大学核能与新能源技术研究院; 出版日期：2019-04-15 出版单位：核科学与工程 年：2019 期：v.39;No.156 基金：国家重大科技专项经费资助项目(ZX069) 语种：中文; 页：HKXY201902015 页数：8 CN：02 ISSN：11-1861/TL 分类号：104-111

摘要

对球床模块式高温气冷堆(HTR-PM)而言,进气事故是高温气冷堆事故分析中重点关注的类型之一。在HTR-PM进气事故中,热气导管双端断裂(DEGB)事故尽管发生概率极低,由于其严重的事故后果仍引起了研究者的大量关注。针对HTR-PM热气导管双端断裂事故,本文利用高温气冷堆专用系统分析程序TINTE-TIIXUW,详细分析了稳定自然循环建立后堆芯及底反射层的氧化情况。结果表明,在保守假设条件下,事故后144 h,燃料最高温度不会超过设计限值,燃料包覆颗粒不会发生裸露,底反射层也不会因氧化发生失效。
        For the 200 MWe high-temperature gas-cooled reactor pebble-bed module(HTR-PM), the air-ingress accident is one of the important types of accident analysis. In air-ingress accidents, even though the probability of the double-ended guillotine break(DEGB)of horizontal gas duct is extremely small, yet it has been paid much attention because of the serious consequences. This paper simulated the DEGB of the horizontal coaxial gas duct of the HTR-PM by using the system analysis software TINTE-TIIXUW. Graphite oxidation of the core and bottom reflector was analyzed in details after the natural circulation was set up. Under the conservative conditions, the simulation results show that the maximum temperature of fuel wouldn't exceed the design limit value, the fuel particles wouldn't be exposed and the bottom reflector wouldn't fail due to oxidation.

引文

[1]石磊,郑艳华.球床模块式高温气冷堆失冷事故特性研究[J].原子能科学技术,2009,43(S2):236-239.
    [2]刘鹏,郑艳华,石磊.高温气冷堆进气事故中自然循环建立时间及影响因素分析[J].原子能科学技术,2014 48(S1):342-346.
    [3]刘鹏.HTR-PM进气事故研究及其关键特性分析[博士学位论文].北京:清华大学核能与新能源技术设计研究院,2016.
    [4]刘宝亭.10 MW高温气冷实验堆进气事故研究[博士学位论文].北京:清华大学核能与新能源技术设计研究院,1998.
    [5]Kim E S,No H C.Experimental study on the oxidation of nuclear graphite and development of an oxidation model[J].Journal of nuclear materials,2006,349(1):182-194.
    [6]Chi S H,Kim G C.Comparison of the oxidation rate and degree of graphitization of selected IG and NBG nuclear graphite grades[J].Journal of nuclear materials,2008,381(1):9-14.
    [7]Oh C H,Kim E S,No H C,et al.Final Report on Experimental Validation of Stratified Flow Phenomena,Graphite Oxidation,and Mitigation Strategies of Air Ingress Accidents[R].USA:Idaho National Laboratory(INL),2011.
    [8]Xu W,Zheng Y,Shi L,et al.Oxidation Analyses of Massive Air Ingress Accident of HTR-PM[J].Science and Technology of Nuclear Installations.2016,2016(3):1-9.
    [9]徐伟,郑艳华,石磊.底反射层氧化对模块式高温气冷堆进气事故的影响分析[J].原子能科学技术,2017 51(4):694-699.
    [10]徐伟.HTR-PM事故工况下石墨氧化分析[博士学位论文].北京:清华大学核能与新能源技术设计研究院,2017.
    [11]Liu P,Chen Z,Zheng Y,et al.Study on air ingress of the200 MWe pebble-bed modular high temperature gas-cooled reactor[J].Annals of Nuclear Energy,2016,98:120-131.
    [12]Moormann R,Hissen H K.Advanced Graphite Oxidation Models.Basic Studies in the Field of High-temperature Engineering,Second Information Exchange Meeting.Paris,France,Oct.10-12,2001.