Recent Improvements in the CUPID Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components

다국어 초록 (Multilingual Abstract)

The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in lightwater nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porousmedia or an open media model for a two-phase flow. In this paper, recent advances in the CUPID code are presented inthree sections. First, the domain decomposition parallel method implemented in the CUPID code is described with theparallel efficiency test for multiple processors. Then, the coupling of CUPID-MARS via heat structure is introduced,where CUPID has been coupled with a system-scale thermal-hydraulics code, MARS, through the heat structure. Thecoupled code has been applied to a multi-scale thermal-hydraulic analysis of a pool mixing test. Finally, CUPID-SG isdeveloped for analyzing two-phase flows in PWR steam generators. Physical models and validation results of CUPID-SGare discussed.

참고문헌 (Reference)

1 P. Coste, "Validation of the Large Interface Model of NEPTUNE_CFD 1.0.8 for Pressurized Thermal Shock (PTS) applications" 253 : 296-310, 2012

2 L. S. Caretto, "Two calculation procedures for steady, three-dimensional flows with recirculation" 1972

3 J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" 한국원자력학회 42 (42): 636-655, 2010

4 H. K. Cho, "Simulation of single- and two-phase natural circulation in the passive condensate cooling tank using the CUPID code" 50 (50): 709-722, 2013

5 강경호, "SEPARATE AND INTEGRAL EFFECT TESTS FOR VALIDATION OF COOLING AND OPERATIONAL PERFORMANCE OF THE APR+ PASSIVE AUXILIARY FEEDWATER SYSTEM" 한국원자력학회 44 (44): 597-610, 2012

6 A. Gupta, "Performance and scalability of preconditioned conjugate gradient methods on parallel computers" 6 (6): 455-469, 1995

7 "OpenMP Application Program Interface, version3.1"

8 N. Kurul, "On the modeling of multidimensional effects in boiling channels" 1991

9 G. Karypis, "Multilevel k-way Partitioning Scheme for Irregular Graphs" 48 (48): 96-129, 1998

10 Han Young Yoon, "Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code" 한국원자력학회 44 (44): 831-846, 2012

11 M. Snir, "MPI: The Complete Reference" MIT Press 1996

12 KAERI Thermal Hydraulic Safety Research Division, "MARS code manual volume V: Models and correlations" KAERI 2009

13 J. J. Jeong, "Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1" 26 (26): 1611-1642, 1999

14 E. D. Grimison, "Correlations and Utilization of New Data on Flow Resistance and Heat Transfer for Cross Flow of Gases over Tube Banks" 59 : 583-, 1937

15 W. H. Kays, "Compact Heat Exchangers" McGraw Hill 1964

16 M. Robert, "CATHARE 2 V2.5: A Fully Validated CATHARE, Version for Various Applications" 2003

17 I. K. Park, "An implicit code coupling of 1-D system code and 3-D in-house CFD code for multi-scaled simulations of nuclear reactor transients" 59 : 80-91, 2013

18 L. W. Keeton, "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)" EPRI 1990

19 J. W. Heistand, "ATHOS and FLOW3 simulation of the FRIGG heated rod bundle experiment" EPRI 1984

20 D. R. Lilies, "A semi-implicit method for two-phase fluid dynamics" 26 : 390-407, 1978

21 H. Y. Yoon, "A Multi-scale analysis of the transient behavior of an advanced safety injection Tank" 62 : 17-25, 2013

22 S. Kim, "2013. An experimental study on the validation of cooling capability for the passive auxiliary feedwater system (PAFS) condensation heat exchanger" 260 : 54-63, 2013