Validation of RELAP5/MOD3.2 code for simulating nucleate pool boiling heat transfer outside vertical tube bundle

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20160902019356

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来源：

(1) Harbin Engineering University, Harbin, Heilongjiang, China | 1600年 / et al.; GLSEQ, LLC/SCI Technologies. Inc; Hitachi-GE Nuclear Energy, Ltd.; Mitsubishi Heavy Industries, Ltd. (MHI); Toshiba Corporation; Westinghouse Electric Company卷 / American Society of Mechanical Engineers (ASME), United States期

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14;

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摘要：

118695

引用

共 43 条

[21] Analysis of the loss of heat sink transients in the secondary circuit of a VVER-1000 using RELAP5/MOD3.2
Abbasi, Somayeh
Hadad, Kamal
ANNALS OF NUCLEAR ENERGY, 2012, 47 : 28 - 37
[22] Pool Boiling Heat Transfer in a Vertical Annulus with a Longer Outside Tube
Kang, Myeong-Gie
TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS B, 2012, 36 (08) : 775 - 782
[23] Pool boiling heat transfer in a vertical annulus with a stepped outside tube
Kang, Myeong-Gie
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2011, 54 (23-24) : 4817 - 4822
[24] Using an IIST 1% cold-leg SBLOCA experiment with passive safety injection to assess the RELAP5/MOD3.2 code
Lee, CH
Huang, IM
Chang, CJ
NUCLEAR TECHNOLOGY, 2001, 135 (02) : 109 - 122
[25] Adjoint sensitivity analysis of the RELAP5/MOD3.2 two-fluid thermal-hydraulic code system - I: Theory
Cacuci, DG
Ionescu-Bujor, M
NUCLEAR SCIENCE AND ENGINEERING, 2000, 136 (01) : 59 - 84
[26] Adjoint sensitivity analysis of the RELAP5/MOD3.2 two-fluid thermal-hydraulic code system - II: Applications
Ionescu-Bujor, M
Cacuci, DG
NUCLEAR SCIENCE AND ENGINEERING, 2000, 136 (01) : 85 - 121
[27] Improvement and validation of the wall heat transfer package of RELAP5/MOD3.3
Wu, Pan
Xiong, Xiaofei
Shan, Jianqiang
Gou, Junli
Zhang, Bin
Zhang, Bo
NUCLEAR ENGINEERING AND DESIGN, 2016, 310 : 418 - 428
[28] Validation of RELAP5/MOD3.2 model on trip off one main coolant pump for VVER 440/V230
Groudev, Pavlin
Stefanova, Antoaneta
NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (12) : 1275 - 1281
[29] Simulation of two loss-of-flow transients in a VVER-1000 nuclear power plant with RELAP5/MOD3.2 system code
Hassan, YA
Moscalu, DR
NUCLEAR TECHNOLOGY, 2000, 129 (01) : 82 - 92
[30] Analysis of experiments for in-tube steam condensation in the presence of noncondensable gases at a low pressure using the RELAP5/MOD3.2 code modified with a non-iterative condensation model
Park, HS
No, HC
Bang, YS
NUCLEAR ENGINEERING AND DESIGN, 2003, 225 (2-3) : 173 - 190

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