Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor

References

• K. E. CARLSON et al., “RELAP5/MOD3 Code Manual Vol. I: Code Structure, System Models, and Solution Methods,” NUREG/CR-5535, EGG-2596, EG&G Idaho, Idaho National Engineering Laboratory (June 1990).
   Google Scholar
• C. D. FLETCHER, L. S. GHAN, J. C. DETERMAN, and H. H. NIELSEN, “Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor,” Nucl. Technol., 106, 31 (1994).
   Web of Science ®Google Scholar
• N. C. J. CHEN, M. W. WENDEL, and G. L. YODER, Jr., “Conceptual Design Loss-of-Coolant Accident Analysis for the Advanced Neutron Source Reactor,” Nucl. Technol., 105, 104 (1994).
   Web of Science ®Google Scholar
• E. ELIAS et al., “Transient Simulation of ALWR Concepts Using RELAP5/MOD2,” 93-WA/HT-72, American Society of Mechanical Engineers (1993).
   Google Scholar
• M. LEE and J. H. WU, “Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor,” Nucl. Technol., 98, 289 (1992).
   Google Scholar
• Y. KOIZUMI, H. KUMAMARU, Y. MIMURA, Y. KUKITA, and K. TASAKA, “Temporary Core Liquid Level Depression During a Cold-Leg Small-Break Loss-of-Coolant Accident, The Effect of Break Size and Power Level,” Nucl. Technol., 96, 290 (1991).
   Web of Science ®Google Scholar
• C. BILLA, F. D’AURIA, and G. M. GALASSI, “Accident Management for a Loss of Feedwater in a Pressurized Water Reactor,” Nucl. Technol., 98, 277 (1992).
   Web of Science ®Google Scholar
• L. REBOLLO, “Assessment of the Code RELAP5/MOD2 Against Loss of Feedwater Without Scram,” Kerntechnik, 58, 20 (Feb. 1993).
   Google Scholar
• 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).
   Web of Science ®Google Scholar
• B. MAVKO, S. PETELIN, and O. GORTNAR, “RELAP5 Modeling of the Westinghouse Model D4 Steam Generator,” Nucl. Technol., 101, 181 (1993).
   Web of Science ®Google Scholar
• Y. A. HASSAN and P. SALIM, “Steady-State Simulations of a 30-Tube Once-Through Steam Generator with the RELAP5/MOD3 and RELAP5/MOD2 Computer Codes,” Nucl. Technol., 96, 123 (1991).
   Web of Science ®Google Scholar
• P. K. JAIN, “Dynamic Model for Pressurized Water Reactor Analysis on Microcomputers,” Nucl. Technol., 72, 301 (1986).
   Web of Science ®Google Scholar
• M. A. BOLANDER et al., “RELAP5 Analyses of Over-cooling Transients in a Pressurized Water Reactor,” Anticipated and Abnormal Plant Transients in Light Water Reactors, Vol. 1, p. 603, Plenum Press (1983).
   Google Scholar
• F. REVENTOS, J. SANCHEZ-BAPTISTA, A. PEREZ NAVAS, and P. MORENO, “Transient Analysis in the Ascó Nuclear Power Plant Using RELAP5/MOD2,” Nucl. Technol., 90, 294 (1990).
   Web of Science ®Google Scholar
• S. PETELIN et al., “Analysis of a Nuclear Plant Transient Caused by a Stuck Spray Valve,” Kerntechnik, 56, 5, 300 (Oct. 1991).
   Google Scholar
• J. J. JEONG, D. Y. OH, H. C. NO, S. H. CHANG, S. J. CHO, H. Y. JUN, and Y. K. LEE, “FISA-2/WS, A Compact Real-Time Simulator for Two-Loop Pressurized Water Reactor Plants,” Nucl. Technol., 90, 356 (1990).
   Web of Science ®Google Scholar
• K. ROSS et al., “RELAP5 Model of the Hope Creek Reactor Vessel and Feedwater/Main Steam Line—Steady State Calculation,” SAIC-219-93-0013, Rev. 2, Science Applications International Corporation (Aug. 10, 1993).
   Google Scholar
• J. A. MOWREY, “Plant Simulation Model Factory Acceptance Test Plan/Procedure for the Browns Ferry Nuclear Plant Reactor Feedwater Control System Project,” Document 01-0515-05-2426-11, Rev. 1, Science Applications International Corporation (Nov. 1994).
   Google Scholar
• “IEEE 488 and VXIbus Control, Data Acquisition, and Analysis,” National Instruments (1994).
   Google Scholar
• “I/A Series Systems, User’s Guides and Information,” The Foxboro Company (1991).
   Google Scholar
• R. A. CURRENT, “Design Description for the Browns Ferry Nuclear Plant Reactor Feedwater Control System Project,” Document 2426-05, Rev. 2, Science Applications International Corporation (May 26, 1994).
   Google Scholar
• “LabVIEW for Windows: User Manual,” National Instruments (Aug. 1993).
   Google Scholar
• Screen prints taken on-site at Browns Ferry Nuclear Plant, Unit 2, Tennessee Valley Authority (Dec. 21, 1993).
   Google Scholar
• D. BAKER, “Calculation of Maximum Feedwater Runout,” letter to M. Bajestani, Tennessee Valley Authority from General Electric Engineering Services (Aug. 30, 1991).
   Google Scholar