Experimental investigation of early initiation of primary cooldown by secondary-side depressurization in a PWR inadequate core-cooling accident

Nuclear Technology

Volumn 129, Issue 2, 2000, Pages 187-200

  Liu, Tay Jian ^a   Chan, Yea Kuang ^a   Ferng, Yuh Ming ^a   Chang, Chien Yeh ^a  

^a INSTITUTE OF NUCLEAR ENERGY RESEARCH   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; CORE DISRUPTIVE ACCIDENTS; DETERIORATION; FAILURE ANALYSIS; HEATING; LOSS OF COOLANT ACCIDENTS; RISK MANAGEMENT; THERMAL STRESS; TRANSIENTS; WATER LEVELS;

CORE COOLING ACCIDENT; HIGH PRESSURE INJECTION SYSTEM; PRIMARY COOLDOWN; RECOVERY ACTION; SECONDARY SIDE DEPRESSURIZATION; SMALL BREAK LOSS OF COOLANT ACCIDENT; THERMAL HYDRAULICS;

PRESSURIZED WATER REACTORS;

EID: 0034140505     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT00-A3056     Document Type: Article

References (27)

1. 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).
2. T. J. LIU, C. H. LEE, T. F. JANG, W. T. HONG, Y. K. CHAN, I. M. HUANG, Y. M. FERNG, and C. J. CHANG, "Cold Leg Small Break LOCA Simulation Tests and Code Assessments on Maanshan Nuclear Power Station," INER-1318, Institute of Nuclear Energy Research (1995).
3. "Report on Small Break Accidents for Westinghouse NSSS System," WCAP-960, Westinghouse Electric Company (1979).
4. N. WATANABE, T. TAMAKOSHI, H. TAKAHASHI, H. KUMAMARU, and M. HIRANO, "Analytical Study on Effect of Reactor Depressurization Measures During LOCA Sequences Followed by Loss of HPI in PWRs," Proc. 3rd Int. Conf. Nucl. Engineering (ICONE-3), Kyoto, Japan, April 23-27, 1995, p. 1303, American Society of Mechanical Engineers/ Japan Society of Mechanical Engineers (1995).
5. "Background Information for Westinghouse Owners Groups Emergency Response Guideline, FR-C. 1: Response to Inadequate Core Cooling," HP-Rev. 1, Westinghouse Electric Company (1983).
6. C. L. NALEZNY, "Summary of Nuclear Regulatory Commission's LOFT Program Experiments," NUREG/CR-3214, U.S. Nuclear Regulatory Commission (1981).
7. E. STREIT, "Results of Semiscale Mod-2C Small-Break Loss-of-Coolant Accident Without HPI (S-NH) Experiment Series," NUREG/CR-4793, U.S. Nuclear Regulatory Commission (1987).
8. T. K. LARSON and G. G. LOOMIS, "Semiscale Program: A Review of Mod-2 Results," Nucl. Safety, 29, 150 (1988).
9. H. ASAKA and Y. KUKITA, "Primary Feed-and-Bleed Experiments at ROSA-IV LSTF," Proc. 6th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics, Grenoble, France, October 5-8, 1993, p. 1361, French Section of the American Nuclear Society (1993).
10. K. KAWANISHI, A. TSUGE, M. FUJIWARE, T. KOHRIYAMA, and H. NAGUMO, "Experimental Study on Heat Removal During Cold Leg Small Break LOCAs in PWRs," J. Nucl. Sci. Technol., 28, 555 (1991).
11. P. CLEMENT, T. CHATAING, and R. DERUAZ, "PWR Accident Management Related Tests: Some BETHSY Results," Proc. 6th Int. Topl. Mtg. Nucl. Reactor Thermal Hydraulics, Grenoble, France, October 5-8, 1993, p. 1377, French Section of the American Nuclear Society (1993).
12. T. J. LIU, C. H. LEE, and C. Y. CHANG, "Experimental Investigation of Early Initiated Secondary Bleed-and-Feed on PWR Inadequate Core Cooling Accident Performed at the IIST Facility," Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6), San Diego, California, May 10-15, 1998, ICONE-6017, American Society of Mechanical Engineers/Japan Society of Mechanical Engineers (1998).
13. P. WEBER, K. J. UMMINGER, and B. SCHOEN, "PWR-Related Integral Safety Experiments in the PKL HI Test Facility SBLOCA Under Beyond-Design-Basis Accident Conditions," Proc. 7th Int. Topl. Mtg. Nucl. Reactor Thermal Hydraulics, Saratoga Springs, New York, September 10-15, 1995, p. 2856 (1995).
14. R. NOEL and R. DERUAZ, "'2' Cold Leg Break at BETHSY Facility," Proc. European Nuclear Society/American Nuclear Society Int. Conf. Thermal Reactor Safety, p. 441 (1989).
15. H. ASAKA, Y. ANODA, Y. KUKITA, and I. OHTSU, "Secondary-Side Depressurization During PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses," J. Nucl. Sci. Technol., 35, 905 (1998).
16. T. K. LARSON, J. L. ANDERSON, and D. J. SHIMECK, "Scaling Criteria and an Assessment of Semiscale Mod-3 Scaling for Small Break Loss-of-Coolant Transients," EGG-M-21082, Idaho National Engineering Laboratory (1982).
17. Y. Y. HSU, Z. Y. WANG, C. UNAL, M. DI MARZO, and K. ALMENAS, "Scaling Modeling for Small Break LOCA Test Facilities," Nucl. Eng. Des., 122, 194 (1990).
18. T. J. LIU, C. H. LEE, and C. Y. CHANG, "Power-Operated Relief Valve Stuck-Open Accident and Recovery Scenarios in the Institute of Nuclear Energy Research Integral System Test Facility," Nucl. Eng. Des., 186, 149 (1998).
19. C. H. LEE, Y. H. CHANG, and Y. J. SU, "Investigation of PWR Natural Circulation at INER Integral System Test Facility," Proc. 6th Int. Topl. Mtg. Nucl. Reactor Thermal Hydraulics, Grenoble, France, October 5-8, 1993, p. 1109 (1993).
20. T. J. LIU, C. H. LEE, W. T. HONG, and Y. H. CHANG, "PWR Station Blackout Transient Simulation in the INER Integral System Test Facility," Proc. 4th Int. Topl. Mtg. Nuclear Thermal Hydraulics, Operations and Safety, Taipei, Taiwan, April 5-8, 1994, p. 55D (1994).
21. T. J. LIU, C. H. LEE, and Y. S. WAY, "IIST and LSTF Counterpart Test on PWR Station Blackout Transient," Nucl. Eng. Des., 167, 357(1997).
22. C. H. LEE, T. J. LIU, W. T. HONG, I. K. CHAN, and I. M. HUANG, "IIST and LSTF/BETHSY Counterpart Tests on PWR Small Break LOCA," Proc. Int. Symp. Two-Phase Flow Modeling and Experimentation, Rome, Italy, October 9-11, 1995, p. 563, Edizioni ETS, Pisa, Italy (1995).
23. T. J. LIU, "IIST and BETHSY Counterpart Tests on PWR Total Loss-of-Feedwater Transient," Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, ICONE-7042 (1999).
24. C. D. FLETCHER and R. A. CALLOW, "Long-Term Recovery of Pressurized Water Reactors Following a Large Break Loss-of-Coolant Accident," Nucl. Eng. Des., 110, 313 (1989).
25. Y. KUKITA, R. R. SCHULTZ, H. NAKAMURA, and J. KATAYAMA, "Quasi-Static Core Liquid Level Depression and Long-Term Core Uncovery During a PWR LOCA," Nucl. Safety, 34, 33 (1993).
26. F. CURCA-TIVIG and J. L. GANDRILLE, "European Pressurized Water Reactor Configuration, Functional Requirements and Efficiency of the Safety Injection System," Proc. IAEA TMC on Progress in Design, R&D and Testing of Safety Systems for Advanced Water Cooled Reactors, Piacenza, Italy, May 16-19, 1995, p. 125, International Atomic Energy Agency (1995).
27. L. M. SHOTKIN and Y. KUKITA, &Implications of the ROSA/AP600 High-and Intermediate-Pressure Test Results,& Nucl. TechnoL, 119, 217 (1997).