The influence of nuclear graphite oxidation on air ingress accident of HTR-PM

被引:13
|
作者
Xu Wei
Sun Jun
Zheng Yanhua
Shi Lei [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China
基金
中国国家自然科学基金;
关键词
HTR-PM; Nuclear grade graphite; Air ingress accident; Bottom reflector;
D O I
10.1016/j.anucene.2017.08.028
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The high temperature gas-cooled reactor pebble bed module (HTR-PM) has wide potential applications in the development of advanced nuclear energy. The double-ended guillotine break (DEGB) of the horizontal coaxial gas duct accident is a kind of beyond design basis accident of HTR-PM, which will result in air ingress into the reactor core. Even though the rare probability of this accident, it still has got a lot of concerns in the safety analyses of HTR-PM, due to the possible severe consequences of the air ingress accident, which would cause oxidation of the graphite material in the reactor. The oxidation of matrix graphite of spherical fuel elements may lead to the exposure of the TRISO fuel particles and the increase of the radioactivity release. The oxidation of the bottom reflector may cause the decrease of mechanical strength of the nuclear grade graphite. Different kinds of nuclear graphite of the bottom reflector will influence the consequences of the DEGB of the horizontal coaxial gas duct accident. This paper mainly analyzed the influence of the nuclear grade graphite used as the bottom reflector on the consequences of this accident by using the system analysis TINTE code. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:1242 / 1248
页数:7
相关论文
共 50 条
  • [21] Oxidation rate of nuclear-grade graphite NBG-18 in the kinetic regime for VHTR air ingress accident scenarios
    Lee, Jo Jo
    Ghosh, Tushar K.
    Loyalka, Sudarshan K.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 438 (1-3) : 77 - 87
  • [22] Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios
    Lee, Jo Jo
    Ghosh, Tushar K.
    Loyalka, Sudarshan K.
    JOURNAL OF NUCLEAR MATERIALS, 2014, 446 (1-3) : 38 - 48
  • [23] GRAPHITE COMPONENT TESTING ON THE LOAD CAPACITY OF THE DOWEL-BRICK STRUCTURE IN HTR-PM
    Shi, Li
    Sun, Libin
    Wang, Zonggang
    Hu, Yuqin
    Zhang, Zhensheng
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 2, 2012, : 157 - 163
  • [24] SEISMIC TEST AND ANALYSES ON DOUBLE-LAYER MODEL OF HTR-PM GRAPHITE STRUCTURE
    Sun, Libin
    Shi, Li
    Wang, Hongtao
    Wang, Haitao
    Hu, Yuqin
    Zhang, Zhensheng
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 2, 2012, : 165 - 173
  • [25] Graphite component testing on the load capacity of the dowel-brick structure in HTR-PM
    Shi, Li
    Sun, Libin
    Wang, Zonggang
    Hu, Yuqin
    Zhang, Zhensheng
    International Conference on Nuclear Engineering, Proceedings, ICONE, 2012, 2 (01): : 157 - 163
  • [26] Analysis of fuel element matrix graphite corrosion in HTR-PM for normal operating conditions
    Yu, Xinli
    Yu, Suyuan
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (04) : 738 - 743
  • [27] Testing the feasibility of multi-modular design in an HTR-PM nuclear plant
    Dong, Zhe
    Zhang, Zuoyi
    Dong, Yujie
    Shi, Lei
    Huang, Xiaojin
    Zhu, Yunlong
    Jiang, Di
    NATURE COMMUNICATIONS, 2025, 16 (01)
  • [28] Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM
    Sun, Ximing
    Dong, Yujie
    Zhou, Yangping
    Li, Zhengcao
    Shi, Lei
    Sun, Yuliang
    Zhang, Zuoyi
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, 54 (02) : 196 - 204
  • [29] Numerical analysis for HTR-PM graphite core structure dynamic response under seismic load
    Lai S.-G.
    Shi L.
    Wang X.-X.
    Sun L.-B.
    Zhang Z.-M.
    Wang W.-J.
    Sun, Li-Bin (slb@tsinghua.edu.cn), 1600, Atomic Energy Press (50): : 2041 - 2047
  • [30] FILTRATION TECHNOLOGY RESEARCH OF GRAPHITE DUST PRODUCED IN SPENT FUEL TRANSPORTATION PROCESS IN HTR-PM
    Wang, Jinhua
    Wang, Bing
    Wu, Bin
    Li, Yue
    Wang, Haitao
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 2, 2018,