References
- ROSA-IV GROUP, “ROSA-IV Large Scale Test Facility (LSTF) System Description,” JAERI-M 84-237, Japan Atomic Energy Research Institute (1985).
- ROSA-IV GROUP, “Supplemental Description of ROSA-IV/LSTF with No.1 Simulated Fuel-Rod Assembly,” JAERI-M 89-113, Japan Atomic Energy Research Institute (1989).
- ROSA-IV GROUP, “ROSA-IV Large Scale Test Facility (LSTF) System Description for Second Simulated Fuel Assembly,” JAERI-M 90-176, Japan Atomic Energy Research Institute (1990).
- M. TANAKA, Y. KUKITA, R. R. SCHULTZ, Y. KOIZUMI, M. KAWAJI, M. OSAKABE, T. YONOMOTO, and K. TASAKA, “A 10% Cold Leg Break Test at ROSA-IV Large Scale Test Facility,” Nucl. Eng. Des., 102, 165 (1987).
- K. TASAKA, Y. KUKITA, Y. KOIZUMI, M. OSAKABE, and H. NAKAMURA, “The Results of 5% Small-Break LOCA Tests and Natural Circulation Tests at the ROSA-IV LSTF,” Nucl. Eng. Des., 108, 37 (1988).
- Y. KOIZUMI, H. KUMAMARU, Y. KUKITA, M. KAWAJI, M. OSAKABE, R. R. SCHULTZ, M. TANAKA, and K. TASAKA, “Blind-Blind Prediction by RELAP5/MOD1 for a 0.1% Very Small Cold-Leg Break Experiment at ROSA-IV Large Scale Test Facility,” Nucl. Technol, 73, 306 (1986).
- Y. KUKITA, K. TASAKA, H. ASAKA, T. YONOMOTO, and H. KUMAMARU, “The Effects of Break Location on PWR Small Break LOCA: Experimental Study at the ROSA-IV LSTF,” Nucl. Eng. Des., 122, 255 (1990).
- H. ASAKA, I. OHTSU, Y. ANODA, Y. KUKITA, and A. OHNUKI, “Core Liquid Level Responses Due to Secondary-Side Depressurization During PWR Small Break LOCA,” J. Nucl. Sci. Technol., 35, 113 (1998).
- K. E. CARLSON et al., “RELAP5/MOD3 Code Manual,” NUREG/CR-5535, EGG-2596, U.S. Nuclear Regulatory Commission, Idaho National Engineering Laboratory (1990).
- H. KUMAMARU and Y. KUKITA, “PWR Cold-Leg Small-Break LOCA with Total HPI Failure: Effect of Break Area on Core Dryout and Intentional Depressurization for Prevention of Excess Core Dryout,” J. Nucl. Sci. Technol., 29, 1162 (1992).
- H. ASAKA, Y. KUKITA, Y. ANODA and T. YONOMOTO, “Computer Code Simulation of Large-Scale Integral Experiments on PWR Thermal-Hydraulic Responses During Accidental Conditions,” Proc. Int. Conf. Supercomputing in Nuclear Applications (SNA ’90), Mito City, Japan, March 12–16, 1990, p. 210 (1990).
- H. K. FAUSKE, “The Discharge of Saturated Water Through Tubes,” AIChE Symp. Ser., 61, 59, 210 (1965).
- K. H. ARDRON and R. A. FURNESS, “A Study of the Critical Flow Models Used in Reactor Blowdown Analysis,” Nucl. Eng. Des., 39, 257 (1976).
- D. W. SALLET, “Thermal Hydraulics of Valves for Nuclear Applications,” Nucl. Sci. Eng., 88, 220 (1984).
- H. ASAKA and Y. KUKITA, “Primary Feed and Bleed Experiments at ROSA-IV LSTF,” Proc. 6th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-6), Grenoble, Isere, France, October 5–9, p. 1361 (1993).