RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS |
Yoon, Han Young
(Korea Atomic Energy Research Institute)
Lee, Jae Ryong (Korea Atomic Energy Research Institute) Kim, Hyungrae (Korea Atomic Energy Research Institute) Park, Ik Kyu (Korea Atomic Energy Research Institute) Song, Chul-Hwa (Korea Atomic Energy Research Institute) Cho, Hyoung Kyu (Department of Nuclear Engineering, Seoul National University) Jeong, Jae Jun (School of Mechanical Engineering, Pusan National University) |
1 | G. Karypis and V. Kumar, "Multilevel k-way Partitioning Scheme for Irregular Graphs," J. Parallel Distrib. Comput. vol. 48, no. 1, pp. 96-129 (1998). DOI ScienceOn |
2 | A. Gupta, V. Kumar and A. Sameh, "Performance and scalability of preconditioned conjugate gradient methods on parallel computers", IEEE Transactions on Parallel and Distributed System, vol. 6, no. 5, pp. 455-469 (1995). DOI |
3 | N. Kurul, M. Z. Podowski, "On the modeling of multidimensional effects in boiling channels," ANS Proceedings of 27th National Heat Transfer Conference, Minneapolis, MN, USA, 1991. |
4 | J. W. Heistand and J. G. Thakkar, "ATHOS and FLOW3 simulation of the FRIGG heated rod bundle experiment," Technical Report NP-3514, EPRI (1984). |
5 | KAERI Thermal Hydraulic Safety Research Division, "MARS code manual volume V: Models and correlations," Technical Report KAERI/TR-3872/2009, KAERI (2009). |
6 | W. H. Kays and A. L. London, "Compact Heat Exchangers", 2nd ed., McGraw Hill, New York (1964). |
7 | E. D. Grimison, "Correlations and Utilization of New Data on Flow Resistance and Heat Transfer for Cross Flow of Gases over Tube Banks," ASME Trans., vol. 59, p. 583 (1937). |
8 | P. Coste, J. Lavieville, J. Pouvreau, C. Baudry, M. Guingo, and A. Douce, "Validation of the Large Interface Model of NEPTUNE_CFD 1.0.8 for Pressurized Thermal Shock (PTS) applications," Nuclear Engineering and Design, vol. 253, pp. 296-310 (2012). DOI |
9 | J. J. Jeong, H. Y. Yoon, I. K. Park, and H. K. Cho, "The CUPID Code Development and Assessment Strategy," Nuclear Engineering and Technology, vol. 42, no. 6, pp. 636-655 (2010). 과학기술학회마을 DOI |
10 | H. Y. Yoon, H. K. Cho, J. R. Lee, I. K. Park, and J. J. Jeong, "Multi-scale thermal-hydraulic analysis of PWRs using the CUPID code," Nuclear Engineering and Technology, vol. 44, no. 8, pp. 831-846 (2012). 과학기술학회마을 DOI ScienceOn |
11 | L. S. Caretto, A. D. Gosman, S. V. Patankar, D. B. Spladding, "Two calculation procedures for steady, three-dimensional flows with recirculation," Proc. 3rd Int. Conf. Numerical Methods in Fluid Dynamics, Paris, France 1972. |
12 | H. Y. Yoon, J. J. Jeong, H. K. Cho, Y. S. Bang, K. W. Seul, "A Multi-scale analysis of the transient behavior of an advanced safety injection Tank," Annals of Nuclear Energy, vol. 62, pp. 17-25 (2013). DOI |
13 | H. K. Cho, S. J. Lee, H. Y. Yoon, K.-H. Kang, and J. J. Jeong, "Simulation of single- and two-phase natural circulation in the passive condensate cooling tank using the CUPID code," Journal of Nuclear Science and Technology, vol. 50, no. 7, pp. 709-722 (2013). DOI |
14 | K.-H. Kang, S. Kim, B.-U. Bae, Y.-J. Cho, Y.-S. Park, B.- J. Yun, "Separate and integral effect tests for validation of cooling and operational performance of the APR+ passive auxiliary feedwater system," Nuclear Engineering and Technology, vol. 44, no. 6, pp. 597-610 (2012). 과학기술학회마을 DOI ScienceOn |
15 | OpenMP Architecture Review Board, OpenMP Application Program Interface, version3.1 (2011). |
16 | M. Snir, S. Otto, S. Huss-Lederman, D. Walker, and J. Dongarra, MPI: The Complete Reference, the MIT Press (1996). |
17 | I. K. Park, J. R. Lee, S. W. Lee, H. Y. Yoon, and J. J. Jeong, "An implicit code coupling of 1-D system code and 3-D in-house CFD code for multi-scaled simulations of nuclear reactor transients," Annals of Nuclear Energy, vol. 59, pp. 80-91 (2013). DOI ScienceOn |
18 | L. W. Keeton, A. K. Singhal, and G. S. Srikantiah, "ATHOS3 Mod-01: A computer program for thermal-hydraulic analysis of steam generator, volume 1: Mathematical and physical models and method of solution (revision 1)," Technical Report NP-4604-CCML, EPRI (1990). |
19 | J. J. Jeong, K. S. Ha, B. D. Chung, and W. J. Lee, "Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1," Annals of Nuclear Energy, vol. 26, no. 18, pp. 1611-1642 (1999). DOI ScienceOn |
20 | D. R. Lilies and W. H. Reed, "A semi-implicit method for two-phase fluid dynamics," Journal of Computational Physics, vol. 26, pp. 390-407 (1978). DOI ScienceOn |
21 | M. Robert, M. Farvacque, M. Parent, and B. Faydide, "CATHARE 2 V2.5: A Fully Validated CATHARE, Version for Various Applications," Proc. 10th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH 10), Seoul, Republic of Korea, October 5-9, 2003. |
22 | S. Kim, B.-U. Bae, Y.-J. Cho, Y.-S. Park, K.-H. Kang, B.- J. Yun, "2013. An experimental study on the validation of cooling capability for the passive auxiliary feedwater system (PAFS) condensation heat exchanger," Nuclear Engineering and Design, vol. 260, pp. 54-63 (2013). DOI |