Effects of gas velocity and break size on steam penetration depth using gas jet into water similarity experiments

被引:11
作者
Zhang, Chaodong [1 ,2 ]
Sa, Rongyuan [1 ]
Zhou, Danna [1 ]
Jiang, Hualei [1 ]
机构
[1] Chinese Acad Sci, Key Lab Neutron & Radiat Safety, Inst Nucl Energy Safety Technol, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
基金
中国国家自然科学基金;
关键词
Lead-based reactor; SGTR; Penetration depth; Visualization; Dimensional analysis; ACTIVATION MARTENSITIC STEEL; TEST BLANKET MODULE; CONCEPTUAL DESIGN; DEVELOPMENT STRATEGY; RUPTURE ACCIDENT; REACTOR; SYSTEM; GENERATION; PROGRESS; ITER;
D O I
10.1016/j.pnucene.2017.02.006
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
A method is given to predict the steam penetration depth under an incidental Steam Generator Tube Rupture (SGTR) accident. Several similar experiments were performed by injecting gas into water to simulate the steam jetting into liquid Lead Bismuth Eutectic (LBE). The steam penetration behaviors including flow regimes and cavity phenomena were captured by visualization method and a semi empirical correlation was modified for the penetration depth based on dimensional analysis and experimental data. The results showed that the penetration depth was proportional to the density ratio of gas jet to liquid coolant, gas velocity, and break size of tube. Further predictions with similarity theory have been conducted. The penetration depth was about 0.7 m during a large break (a double-ended break) of one SG cooling tubes under a postulated SGTR accident of lead-based reactor. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:38 / 44
页数:7
相关论文
共 40 条
  • [1] Ciampichetti A., 2012, INT WORKSH INN NUCL
  • [2] Cinotti L, 2007, PROJ REV GEN NUCL, P30
  • [3] Lead-cooled system design and challenges in the frame of Generation IV International Forum
    Cinotti, Luciano
    Smith, Craig F.
    Sekimoto, Hiroshi
    Mansani, Luigi
    Reale, Marco
    Sienicki, James J.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (03) : 245 - 253
  • [4] DINH T. N., 2007, PROC ICAPP 2007
  • [5] Preliminary investigation on the primary heat exchanger lower head rupture accident of forced circulation LBE-cooled fast reactor
    Gu, Zhixing
    Wang, Gang
    Bai, Yunqing
    Song, Yong
    Zhao, Zhumin
    [J]. ANNALS OF NUCLEAR ENERGY, 2015, 81 : 84 - 90
  • [6] Han X., 1996, ENG CHEM METALLURGY, V17, P164
  • [7] Progress in development of China Low Activation Martensitic Steel for fusion application
    Huang, Q.
    Li, C.
    Li, Y.
    Chen, M.
    Zhang, M.
    Peng, L.
    Zhu, Z.
    Song, Y.
    Gao, S.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 : 142 - 146
  • [8] Status and strategy of fusion materials development in China
    Huang, Q. Y.
    Wu, Y. C.
    Li, J. G.
    Wan, F. R.
    Chen, J. L.
    Luo, G. N.
    Liu, X.
    Chen, J. M.
    Xu, Z. Y.
    Zhou, X. G.
    Ju, X.
    Shan, Y. Y.
    Yu, J. N.
    Zhu, S. Y.
    Zhang, P. Y.
    Yang, J. F.
    Chen, X. J.
    Dong, S. M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 400 - 404
  • [9] Study of irradiation effects in China low activation martensitic steel CLAM
    Huang, QY
    Li, JG
    Chen, YX
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 268 - 272
  • [10] A Critical Review of the Modified Froude Number in Ladle Metallurgy
    Krishnapisharody, K.
    Irons, G. A.
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS B-PROCESS METALLURGY AND MATERIALS PROCESSING SCIENCE, 2013, 44 (06): : 1486 - 1498