CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment |
Ye, Linrong
(State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University)
Yu, Hao (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) Wang, Mingjun (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) Wang, Qianglong (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) Tian, Wenxi (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) Qiu, Suizheng (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) Su, G.H. (State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology, Xi'an Jiaotong University) |
1 | T. Feng, D. Zhang, P. Song, W. Tian, W. Li, G.H. Su, S. Qiu, Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5, Ann. Nucl. Energy 109 (2017) 318-326. DOI |
2 | R.C. Jones, Boron Dilution Reactivity Transients A Regulatory Perspective, Nuclear Energy Agency of the OECD (NEA), 1996, pp. 24-28. |
3 | J. Li, M. Wang, D. Fang, J. Wang, D. Liu, W. Tian, S. Qiu, G.H. Su, CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel, Ann. Nucl. Energy 153 (2021). |
4 | V.H. Ransom, J. Trapp, R. Wagner, RELAP5/MOD3. 3 Code Manual Volume IV: Models and Correlations NUREG/CR-5535/Rev 1, Idaho National Engineering Laboratory, 2001. |
5 | A. Petruzzi, F. D'Auria, Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures, in: Science and Technology of Nuclear Installations 2008, 2008, p. 460795. |
6 | J. Mahaffy, B. Chung, C. Song, F. Dubois, E. Graffard, F. Ducros, M. Heitsch, M. Scheuerer, M. Henriksson, E. Komen, F. Moretti, T. Morii, P. Muehlbauer, U. Rohde, B.L. Smith, T. Watanabe, G. Zigh, Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications, Nuclear Energy Agency of the OECD (NEA), 2007, p. 166. |
7 | B.J. Daly, Three-dimensional Calculations of Transient Fluid-Thermal Mixing in the Downcomer of the Calvert Cliffs-1 Plant Using SOLA-PTS, Los Alamos National Lab, 1984. |
8 | D.L. Aumiller, E.T. Tomlinson, W.L. Weaver, An integrated relap5-3d and multiphase cfd code system utilizing a semi-implicit coupling technique, Nucl. Eng. Des. 216 (2002) 77-87. DOI |
9 | H. Yu, M. Wang, R. Cai, D. Zhang, W. Tian, S. Qiu, G.H. Su, Development and validation of boron diffusion model in nuclear reactor core subchannel analysis, Ann. Nucl. Energy 130 (2019) 208-217. DOI |
10 | A. Tanrikut, O. Yesin, In-tube steam condensation in the presence of air under transient conditions, in: Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, 2007. NUREG/IA-0210. |
11 | D. Bestion, System Code Models and Capabilities, Thicket-2008, Italy, 2008, p. 486. |
12 | A. Papukchiev, M. Jeltsov, K. Koop, P. Kudinov, G. Lerchl, Comparison of different coupling CFDeSTH approaches for pre-test analysis of a TALL-3D experiment, Nucl. Eng. Des. 290 (2015) 135-143. DOI |
13 | N. Anderson, Y. Hassan, R. Schultz, Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code, Nucl. Eng. Des. 238 (2008) 274-279. DOI |
14 | D. Aumiller, E. Tomlinson, R.J.N.E. Bauer, Design, in: A Coupled RELAP5-3D/CFD Methodology with a Proof-Of-Principle Calculation, vol. 205, 2001, pp. 83-90. |
15 | A. Papukchiev, G. Lerchl, C. Waata, T.J.P.o.N. Frank, Extension of the Simulation Capabilities of the 1D System Code ATHLET by Coupling with the 3D CFD Software Package ANSYS CFX, 2009. |
16 | T. Grunloh, A. Manera, Comparison of overlapping and separate domain coupling methods, in: NURETH-16: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015. |
17 | H. Yu, H. Ju, M. Wang, J. Zhang, S. Qiu, W. Tian, G.H. Su, Study of boron diffusion models and dilution accidents in nuclear reactor: a comprehensive review, Ann. Nucl. Energy 148 (2020) 107659. DOI |
18 | D. Pialla, D. Tenchine, S. Li, P. Gauthe, A. Vasile, R. Baviere, N. Tauveron, F. Perdu, L. Maas, F. Cocheme, K. Huber, X. Cheng, Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project, Nucl. Eng. Des. 290 (2015) 78-86. DOI |
19 | M. Wang, Y. Wang, W. Tian, S. Qiu, G.H. Su, Recent progress of CFD applications in PWR thermal hydraulics study and future directions, Ann. Nucl. Energy 150 (2021) 107836. DOI |
20 | W. Li, X. Wu, D. Zhang, G. Su, W. Tian, S. Qiu, Preliminary study of coupling CFD code FLUENT and system code RELAP5, Ann. Nucl. Energy 73 (2014) 96-107. DOI |
21 | M. Gavrilas, K. Kiger, International standard problem (ISP) No. 43 rapid boron dilution transient tests for code verification, in: Nucl. Energy Agency Comparison Report NEA/CSNI, 2001. NEA/CSNI/R(2000)22. |
22 | H. Prasser, G. Grunwald, T. Hohne, S. Kliem, U. Rohde, F.J.N.T. Weiss, Coolant Mixing in a PWR-Deboration Transients, Steam Line Breaks and Emergency Core Cooling Injection-Experiments and Analyses, vol. 143, 2003, pp. 37-56. |
23 | R. Baviere, N. Tauveron, F. Perdu, E. Garre, S. Li, A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phenix Reactor Natural Circulation Test, Nucl. Eng. Des. 277 (2014) 124-137. DOI |