CORE THERMAL HYDRAULIC BEHAVIOR DURING THE REFLOOD PHASE OF COLD-LEG LBLOCA EXPERIMENTS USING THE ATLAS TEST FACILITY
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Cho, Seok
(Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) Kang, Kyoung-Ho (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) Baek, Won-Pil (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) Kim, Yeon-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) |
1 |
Park, H.S., et al., “Overview of the KAERI LBLOCA reflood test program using the ATLAS facility,” The |
2 | Hochreiter, L. E., Lee, R., Singh, A., Kozuch, J. P., “FLECHT SEASET program final report,” Westinghouse Electric Co., WCAP-10926, UNREG/CP-4167, (1985) |
3 | Sun, K.H., Duffey, R.B., and Peng, C.M., “The prediction of two-phase mixture level and hydro-dynamically controlled dryout under low flow conditions,” Int. J. Multiphase Flow, 7(6), 521, (1981) DOI ScienceOn |
4 | Cermak, J.O., Kitzes, A.S., Cadek, F.F., Leyse, R.H., Dominicis, D.P., "PWR full length emergency coolant heat transfer (FLECTH) Group I test report," Westinghouse Electric Co., WCAP-7435, (1970) |
5 | Silva, H.C., Parvez, P., Choe, W. G., “Effect of downcomer boiling on LOCA PCT for a 4-loop PWR with a large-dry containment,” The 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, Oct. 5-9, (2003) |
6 | Cho, S., Moon, S.K., Chun, S.Y., Kim, Y.S., Baek, W.P., 2007. “Spacer grid effects during a reflood in an annulus flow channel,” J. Nucl. Sci. and Tech., 44(7), 967, (2007) DOI ScienceOn |
7 | Park, H.S., et al., “Calculation sheet for the basic design of the ATLAS fluid system,” KAERI technical report, KAERI/TR-3333/2007, (2007) |
8 | Wallis, G. B., “One-dimensional two-phase flow,” McGrew-Hill Book Company, (1969) |
9 | Yadigaroglu, G., “The reflooding phase of the LOCA in PWRs, Part I: Core heat transfer and fluid flow,” Nucl. Safety, 19(1), 20, (1978) |
10 | Kang, K.-H., Moon, S.-K., Park, H.-S., Cho, S., Choi, K.-Y., “ATLAS facility description report,” KAERI technical report, KAERI/TR-3754/2009, (2009) |
11 | Baek, W.P., Song, C.H., Yun, B.J., Kwon, T.S., Moon, S.K., Lee, S.J., “KAERI Integral Effect Test Program and the ATLAS Design,” Nuclear Technology, 152, 183, (2005) |
12 | Ishii, M., and Kataoka, I., “Similarity Analysis and Scaling Criteria for LWRs Under Single Phase and Two-Phase Natural Circulation,” NUREG/CR-3267, ANL-83-32, Argonne National Laboratory, (1983) |
13 | Okubo, T., and Murao, Y., "Assessment of core thermohydrodynamic models of REFLA-1D code with CCTF data for reflood phase of PWR-LOCA," J. Nucl. Sci. Tech., 22, 983, (1985) DOI ScienceOn |
14 | Cho, S., Moon, S.K., Choi, K.Y., Park, J.K., Baek, W.P., “ Rewetting of a vertical hot surface of a simulated 6x6 rod bundle during a reflood phase,” NTHAS5: Fifth Korea-Japan Symposium on Nuclear Thermal Hydraulic and Safety, Jeju, Korea, Nov., (2006) |
15 | Iguchi, T., Iwamura, T., Akimoto, H., 'SCTF-III test plan and recent SCTF-III test results,' Nucl. Eng. Des., 108, 241, (1983) DOI ScienceOn |
16 |
Cho, S., Euh, D.J., Kim, B.D., Choi, K.Y., Park, H.S., Kim, Y.S., Baek, W.P., “Description of the data acquisitioncontrol system and instrumentation of the atlas test facility,” WORTH-3 (The |
17 | Weiss, P., “UPTF experiment: principal full scale test results for enhanced knowledge of large break LOCA scenarios in PWR,” NURETH-4, Vol.1, pp.60-66, (1989) |
18 | Martini, R., Premoli, A.,”Bottom flooding experiments with simple geometries under different ECC conditions,” Energia Nucleare, 20(10), 540, (1973) |
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