참고문헌
- Yadigaroglu, G., “The reflooding phase of the LOCA in PWRs, Part I: Core heat transfer and fluid flow,” Nucl. Safety, 19(1), 20, (1978)
- 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) https://doi.org/10.3327/jnst.22.983
- 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)
- Iguchi, T., Iwamura, T., Akimoto, H., 'SCTF-III test plan and recent SCTF-III test results,' Nucl. Eng. Des., 108, 241, (1983) https://doi.org/10.1016/0029-5493(88)90070-2
- 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)
- 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)
- Park, H.S., et al., “Calculation sheet for the basic design of the ATLAS fluid system,” KAERI technical report, KAERI/TR-3333/2007, (2007)
-
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
$3^{rd}$ Sino-Korea Workshop in Nuclear Reactor Thermal Hydraulics), Chengdu, China, Aug. (2007) -
Park, H.S., et al., “Overview of the KAERI LBLOCA reflood test program using the ATLAS facility,” The
$7^{th}$ International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), Seoul, Korea, Oct. 5-9, paper 350, (2008) - Martini, R., Premoli, A.,”Bottom flooding experiments with simple geometries under different ECC conditions,” Energia Nucleare, 20(10), 540, (1973)
- Wallis, G. B., “One-dimensional two-phase flow,” McGrew-Hill Book Company, (1969)
- Hochreiter, L. E., Lee, R., Singh, A., Kozuch, J. P., “FLECHT SEASET program final report,” Westinghouse Electric Co., WCAP-10926, UNREG/CP-4167, (1985)
- 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)
- 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) https://doi.org/10.1016/0301-9322(81)90056-2
- 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)
- 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) https://doi.org/10.3327/jnst.44.967
- 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)
- 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)
피인용 문헌
- A balance procedure for calculating the model fuel assemblies reflooding during design basis accident and its verification on PARAMETER test facility vol.60, pp.5, 2013, https://doi.org/10.1134/S0040601513050030
- Balance method of calculating the characteristics of a repeated flooding of nuclear reactors in projected accidents vol.86, pp.2, 2013, https://doi.org/10.1007/s10891-013-0843-x