Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor |
Sun, Lin
(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)
Peng, Minjun (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) Xia, Genglei (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) Lv, Xing (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) Li, Ren (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) |
1 | Y. Bae, Y.I. Kim, C.T. Park, CFD analysis of flow distribution at the core inlet of SMART, Nucl. Eng. Des 258 (2013) 19-25. DOI |
2 | M.F. Robbe, M. Lepareux, E. Treille, Y. Cariou, Numerical simulation of a hypothetical core disruptive accident in a small-scale model of a nuclear reactor, Nucl. Eng. Des 223 (2003) 159-196. DOI |
3 | J.H. Jeong, B.S. Han, Coolant flow field in a real geometry of PWR downcomer and lower plenum, Ann. Nucl. Energy 35 (2008) 610-619. DOI |
4 | K.M. Kim, B.I. Lee, H.H. Cho, J.S. Park, Y.J. Chung, Numerical study on thermo-hydrodynamics in the reactor internals of SMART, Nucl. Eng. Des 241 (2011) 2536-2543. DOI |
5 | Y.I. Kim, Y. Bae, Y.J. Chung, K.K. Kim, CFD simulation for thermal mixing of a SMART flow mixing header assembly, Ann. Nucl. Energy 85 (2015) 357-370. DOI |
6 | B.H. Yan, G. Zhang, H.Y. Gu, CFD analysis of the effect of rolling motion on the flow distribution at the core inlet, Ann. Nucl. Energy 41 (2012) 17-25. DOI |
7 | S. Lim, Y. Choi, K. Ha, K. Park, N. Park, Y. Park, K. Jeong, J. Park, Dynamic characteristics of a perforated cylindrical shell for flow distribution in SMART, Nucl. Eng. Des 241 (2011) 4079-4088. DOI |
8 | K. Min, B. In, D. Lee, H. Hee, K. Hoon, Experimental and numerical study on local pressure distributions in a system-integrated modular reactor, Ann. Nucl. Energy 47 (2012) 216-224. DOI |
9 | H.K. Versteeg, W. Malalasekera, An Introduction to Computational Fluid Dynamics: The Finite Volume Method, second ed., Pearson, London, 2007. |
10 | ANSYS Inc, FLUENT 15.0 user's guide, 2013. |
11 | P.J. Roache, Perspective: a method for uniform reporting of grid refinement studies, J. Fluids Eng 116 (1994) 405-413. DOI |
12 | G.L. Xia, G.H. Su, M.J. Peng, Analysis of flow distribution in plate-type core affected by uneven inlet temperature distribution, Ann. Nucl. Energy 92 (2016) 333-344. DOI |
13 | F. Menter, B. Hemstrom, M. Henriksson, R. Karlsson, A. Latrobe, P. Muhlbauer, M. Scheuerer, B. Smith, T. Takacs, S. Willemsen, ECORA Contract No. FIKS-CT-2001-00154 CFD best practice guidelines for CFD code validation for reactor safety applications, 2002, 1-46. |
14 | U. Rohde, T. Hohne, S. Kliem, B. Hemstrom, M. Scheuerer, T. Toppila, A. Aszodi, I. Boros, I. Farkas, P. Muhlbauer, L. Vyskocil, J. Klepac, J. Remis, T. Dury, Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor-validation of CFD codes, Nucl. Eng. Des 237 (2007) 1639-1655. DOI |
15 | G.L. Xia, Analysis of the Impact of OTSG Grouping Run on Reactor Core Thermal-hydraulic Characteristics, D. Eng. Dissertation, Harbin Engineering University, 2014. |
16 | M. Andreani, A. Takacs, A. Latrobe, J. Lillington, S. Assurance, Evaluation of Computational Fluid Dynamic Methods for Reactor Safety Analysis Contract FIKS-CT-2001-00154 Review of CFD Applications in Primary Loop and Recommendations FZR, Germany, 2003. |
17 | D. Bestion, M. Scheuerer, Recommendation on Use of CFD Codes for Nuclear Reactor Safety Analysis Contribution, 2002. |
18 | M. Scheuerer, M. Heitsch, F. Menter, Y. Egorov, I. Toth, D. Bestion, S. Pigny, H. Paillere, A. Martin, M. Boucker, E. Krepper, S. Willemsen, P. Muhlbauer, M. Andreani, B. Smith, R. Karlsson, M. Henriksson, B. Hemstrom, I. Karppinen, G. Kimber, Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA), Nucl. Eng. Des 235 (2005) 359-368. DOI |
19 | G.L. Xia, M.J. Peng, X. Du, Analysis of load-following characteristics for an integrated pressurized water reactor, Int. J. Energy Res 38 (2014) 380-390. DOI |
20 | S.U. Khan, M.J. Peng, Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor, Int. J. Energy Res 37 (2013) 1709-1717. DOI |
21 | W.Q. Xu, M.J. Peng, Research on ideal steady-state programming control strategy of integral PWR, Chin. J. Nucl. Sci. Eng 30 (2010) 1-8. |
22 | L. Sun, M. Peng, G. Xia, Study on natural circulation and its transition process for IP200, Trans. Am. Nucl. Soc 111 (2014) 1467-1470. |
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