References
- U.S. NRC, “Loss of Residual Heat Removal System-Diablo Canyon, Unit 2, April 10, 1987,” NUREG-1269, U.S. Nuclear Regulatory Commission (1987).
- U.S. NRC, “Loss of Vital AC Power and the Residual Heat Removal System During Mid-Loop Operations at Vogtle Unit 1 on March 20, 1990,” NUREG-1410, U.S. Nuclear Regulatory Commission (June 1990).
- N. FUJITA and D. A. RICE, “Core Boiling During Mid-loop Operation”, Nucl. Technol., 93, 36 (1991).
- H. NAKAMURA, J. KATAYAMA and Y. KUKITA, “RELAP5 Code Analysis of a ROSA-IV/LSTF Experiment Simulating a Loss of Residual Heat Removal Event During PWR Mid-Loop Operation”, Proc. 5th Int. Topl. Mtg. Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, Utah, September 21–24, 1992, Vol. V, p. 1333, American Nuclear Societys (1992).
- Y. A. HASSAN and L. L. RAJA, “Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code”, Nucl. Technol., 103, 310 (1993).
- S. BANERJEE and Y. A. HASSAN, “RELAP5/MOD3 Simulation of the RHR System During Midloop Operation Experiment Conducted at the ROSA-IV Large Scale Test Facility”, Proc. Int. Conf. New Trends in Nuclear System Thermohy-draulics, Pisa, Italy, May 30–June 2, 1994, p. 407, University of Rome (1994).
- U.S. NRC, “RELAP5/MOD3 Code Manual: User’s Guide and Input Requirements,” EG&G Idaho, NUREG/CR-5535, INEL-95/0174, Volumes 1 through 5, U.S. Nuclear Regulatory Commission (Aug. 1995).
- ROSA-IV GROUP, “ROSA-IV Large Scale Test Facility (LSTF) System Description,” JAERI-M 84-273, Japan Atomic Energy Research Institute (Jan. 1985).
- H. NAKAMURA and Y. KUKITA, “ PWR Thermal-Hydraulic Phenomena Following Loss of Residual Heat Removal (RHR) During Mid-Loop Operation”, Proc. Int. Conf. New Trends in Nuclear System Thermohydraulics, Pisa, Italy, May 30–June 2, 1994, p. 77, University of Rome (1994).
- KEPCO, “Final Safety Analysis Report for Yong Gwang Nuclear Power Plants Units 3&4,” Korea Electric Power Company (Mar. 1996).
- K. W. SEUL, Y. S. BANG and H. J. KIM, “Assessment of RELAP5/MOD3.2 with LSTF Experiment Simulating a Loss of Residual Heat Removal Event During Mid-Loop Operation,” NUREG/IA-0143, U.S. Nuclear Regulatory Commission (Aug. 1998).
- Y.-M. FERNG and C.-H. LEE, “Assessment of the Simulation Capability of RELAP5/MOD3 Compared with IIST Tests for Loss of the Residual Heat Removal System During Mid-loop Operation”, Nucl. Technol., 116, 19 (1996).