Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid |
Liu, Wei
(State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China)
Shang, Zemin (School of Mechanical, Electronic and Control Engineering, Beijing Jiaotong University) Yang, Shihao (School of Mechanical, Electronic and Control Engineering, Beijing Jiaotong University) Yang, Lixin (School of Mechanical, Electronic and Control Engineering, Beijing Jiaotong University) Tian, Zihao (School of Mechanical, Electronic and Control Engineering, Beijing Jiaotong University) Liu, Yu (State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China) Chen, Xi (State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China) Peng, Qian (State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China) |
1 | Q. Li, M. Avramova, Y. Jiao, P. Chen, J. Yu, Z. Pu, J. Chen, CFD prediction of critical heat flux in vertical heated tubes with uniform and Nonuniform heat flux, Nucl. Eng. Des. 326 (2018) 403-412. DOI |
2 | S.R.G. Vadlamudi, A.K. Nayak, CFD simulation of Departure from Nucleate Boiling in vertical tubes under high pressure and high flow conditions, Nucl. Eng. Des. 352 (2019) 110150. DOI |
3 | B.S. Shin, S.H. Chang, CHF experiment and CFD analysis in a 2×3 rod bundle with mixing vane, Nucl. Eng. Des. 239 (2009) 899-912. DOI |
4 | S.J. Kim, Evaluation of CASL Boiling Model for DNB Performance in Full Scale 5x5 Fuel Bundle with Spacer Grids, United States, 2018. |
5 | J. Yan, L.D. Smith III, Z. Karoutas, Departure from Nucleate Boiling Modeling Development for PWR Fuel, 2013. |
6 | W. Liu, Z. Shang, L. Yang, Y. Liu, Y. Hu, Y. Liu, Numerical investigation of the CHF in a vertical round tube and a single rod channel based on the eulerian two-fluid model, Prog. Nucl. Energy 135 (2021). |
7 | M. Colombo, M. Fairweather, Accuracy of Eulerian-Eulerian, two-fluid CFD boiling models of subcooled boiling flows, Int. J. Heat Mass Tran. 103 (2016) 28-44. DOI |
8 | X. Dong, Z. Zhang, D. Liu, Z. Tian, G. Chen, Numerical investigation of the effect of grids and turbulence models on Critical Heat Flux in a vertical pipe, Front. Energy Res. 6 (2018) 58. DOI |
9 | A. Tomiyama, I. Kataoka, I. Zun, T. Sakaguchi, Drag coefficients of single bubbles under normal and micro gravity conditions, JSME Int. J., B 41 (1998) 472-479. |
10 | S.P. Antal, R.T. Lahey Jr., J.E. Flaherty, Analysis of phase distribution in fully developed laminar bubbly two-phase flow, Int. J. Multiphas. Flow 17 (1991) 635-652. DOI |
11 | G. Kocamustafaogullari, Pressure dependence of bubble departure diameter for water, Int. Commun. Heat Mass Tran. 10 (1983) 501-509. DOI |
12 | A. Tomiyama, Struggle with computational bubble dynamics, Multiphas. Sci. Technol. 10 (1998) 369-405. DOI |
13 | N. Kurul, M.Z. Podowski, On the Modeling of Multidimensional Effects in Boiling Channels, 27th National Heat Transfer Conference, Minneapolis, Minnesota, USA, 1991. |
14 | J. Weisman, B.S. Pei, Prediction of critical heat flux in flow boiling at low qualities, Int. J. Heat Mass Tran. 26 (1983) 1463-1477. DOI |
15 | R. Cole, A photographic study of pool boiling in the region of the critical heat flux, AIChE J. 6 (1960) 533-538. DOI |
16 | D.I.F.T. Salnikova, Two-phase CFD Analyses in Fuel Assembly Sub-channels of Pressurized Water Reactors under Swirl Conditions, 2010. |
17 | D. Chen, Y. Xiao, S. Xie, D. Yuan, X. Lang, Z. Yang, Y. Zhong, Q. Lu, Thermal-hydraulic performance of a 5 × 5 rod bundle with spacer grid in a nuclear reactor, Appl. Therm. Eng. 103 (2016) 1416-1426. DOI |
18 | R. Zhang, T. Cong, G. Su, J. Wang, S. Qiu, Investigation on the critical heat flux in typical 5 by 5 rod bundle at conditions prototypical of PWR based on CFD methodology, Appl. Therm. Eng. 179 (2020). |
19 | D.C. Groeneveld, J. Shan, A.Z. Vasic, L.K.H. Leung, A. Durmayaz, J. Yang, S. Cheng, A. Tanase, The 2006 CHF look-up table, Nucl. Eng. Des. 237 (2007) 1909-1922. DOI |
20 | K. Ikeda, Y. Makino, M. Hoshi, Single-phase CFD applicability for estimating fluid hot-spot locations in a 5×5 fuel rod bundle, Nucl. Eng. Des. 236 (2006) 1149-1154. DOI |
21 | J. Lei, S. Bu, J. Jiang, H. Liu, D. Yuan, D. Chen, Numerical investigation on thermal-hydraulic performance in 7×7 rod bundle with spacer grid and guide tubes, Int. J. Therm. Sci. 160 (2021). |
22 | A.D. Burns, T. Frank, I. Hamill, J.-M. Shi, The Favre Averaged Drag Model for Turbulent Dispersion in Eulerian Multi-phase Flows, ICMF, 2004, pp. 1-17. |
23 | T.R. Auton, J.C.R. Hunt, M. Prud'Homme, The force exerted on a body in inviscid unsteady Nonuniform rotational flow, J. Fluid Mech. 197 (1988) 241-257. DOI |
24 | T. Hibiki, M. Ishii, Active nucleation site density in boiling systems, Int. J. Heat Mass Tran. 46 (2003) 2587-2601. DOI |
25 | R. Zhang, T. Cong, W. Tian, S. Qiu, G. Su, Effects of turbulence models on forced convection subcooled boiling in vertical pipe, Ann. Nucl. Energy 80 (2015) 293-302. DOI |
26 | G.G. Bartolomei, V.M. Chanturiya, Experimental study of true void fraction when boiling subcooled water in vertical tubes[J], Therm. Eng. 14 (2) (1967) 123-128. |
27 | M.A. Navarro, A.A.C. Santos, Evaluation of a numeric procedure for flow simulation of a 5 × 5 PWR rod bundle with a mixing vane spacer, Prog. Nucl. Energy 53 (2011) 1190-1196. DOI |
28 | C.C. Liu, Y.M. Ferng, C.K. Shih, CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly, Appl. Therm. Eng. 40 (2012) 389-396. DOI |
29 | Y. Wang, M. Wang, H. Ju, M. Zhao, D. Zhang, W. Tian, T. Liu, S. Qiu, G.H. Su, CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR, Nucl. Eng. Technol. 52 (2020) 1386-1395. DOI |
30 | S. Cheng, H. Chen, X. Zhang, CFD analysis of flow field in a 5 × 5 rod bundle with multi-grid, Ann. Nucl. Energy 99 (2017) 464-470. DOI |
31 | M.A. Nemitallah, M.A. Habib, R. Ben Mansour, M. El Nakla, Numerical predictions of flow boiling characteristics: current status, model setup and CFD modeling for different Nonuniform heating profiles, Appl. Therm. Eng. 75 (2015) 451-460. DOI |
32 | R. Thakrar, J. Murallidharan, S.P. Walker, CFD investigation of nucleate boiling in non-circular geometries at high pressure, Nucl. Eng. Des. 312 (2017) 410-421. DOI |
33 | C.R. Mali, V. Vinod, A.W. Patwardhan, Comparison of phase interaction models for high pressure subcooled boiling flow in long vertical tubes, Nucl. Eng. Des. 324 (2017) 337-359. DOI |
34 | T. Cong, R. Zhang, L. Chen, X. Zhang, T. Yu, Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model, Ann. Nucl. Energy 114 (2018) 413-426. DOI |
35 | Q. Li, Y. Jiao, M. Avramova, P. Chen, J. Yu, J. Chen, J. Hou, Development, verification and application of a new model for active nucleation site density in boiling systems, Nucl. Eng. Des. 328 (2018) 1-9. DOI |
36 | R. Zhang, T. Cong, W. Tian, S. Qiu, G. Su, Prediction of CHF in vertical heated tubes based on CFD methodology, Prog. Nucl. Energy 78 (2015) 196-200. DOI |
37 | S.J. Kim, B. Okhuysen, E. Demarly, E. Baglietto, CFD Study of a Multi-phase Subcooled Flow Boiling Model and the Evaluation of the Model's Predictive Capability for Boiling Characteristics, NUTHOS-11: the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, 2016. |
38 | X. Dong, J.P. Duarte, D. Liu, J. Wang, Z. Zhang, Z. Tian, Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel, Ann. Nucl. Energy 121 (2018) 203-209. DOI |
39 | H. Pothukuchi, S. Kelm, B.S.V. Patnaik, B.V.S.S.S. Prasad, H.J. Allelein, CFD modeling of critical heat flux in flow boiling: validation and assessment of closure models, Appl. Therm. Eng. 150 (2019) 651-665. DOI |
40 | J.S. Murallidharan, B.V.S.S.S. Prasad, B.S.V. Patnaik, G.F. Hewitt, V. Badalassi, CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling, Int. J. Heat Mass Tran. 103 (2016) 211-230. DOI |
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