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Nuclear Technology Volume 113, 1996 - Issue 3
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Technical Paper

Use of the Chinshan Plant Analyzer for Analysis of a Main-Steam-Isolation-Valve-Closure Anticipated Transient Without Scram

Shih-Jen WangInstitute of Nuclear Energy Research, P.O. Box 3-3 Lung-tan, Taoyuan, Taiwan 32500
,
Shih-Hsiin ChangInstitute of Nuclear Energy Research, P.O. Box 3-3 Lung-tan, Taoyuan, Taiwan 32500
&
Ling-Yao ChouTaiwan Power Company 242 Roosevelt Road, Taipei, Taiwan
Pages 280-290 | Published online: 12 May 2017

References

  • “Reactor Safety Study-An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants”, WASH-1400, NUREG-751014, U.S. Nuclear Regulatory Commission (Oct. 1975).
  • “Probabilistic Risk Assessment, Chinshan Nuclear Power Station Unit 1”, Atomic Energy Council, Taiwan (Aug. 1991).
  • L. NEYMOTIN, G. SLOVIK, E. CAZZOLI, and P. SAHA, “Evaluation of BWR Emergency Procedure Guidelines for BWR ATWS Using RAMONA-3B Code,” Proc. 3rd Int. Topl. Mtg. Reactor Thermal Hydraulics, Newport, Rhode Island, October 15–18, 1985, Vol. 1, p. 3.D-1, American Nuclear Society (1985).
  • S.-J. WANG, C.-S. CHIEN, J.-Y. JANG, and S.-C. LEE, “Development of the Chinshan Plant Analyzer and Its Assessment with Plant Data,” Nucl. Technol., 102, 297 (1993).
  • S.-J. WANG, C.-S. CHIEN, and J.-Y. JANG, “Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer,” Nucl. Technol., 103, 131 (1993).
  • S.-J. WANG and C.-S. CHIEN, “Optimizing Feedwater Control System Performance with the Chinshan Plant Analyzer,” Nucl. Technol., 103, 403 (1993).
  • “Final Safety Analysis Report of the Chinshan Nuclear Power Station”, Taiwan Power Company.
  • W. WULFF, H. S. CHENG, S. V. LEKACH, and A. N. MALLEN, “The BWR Plant Analyzer”, NUREG/CR-3943, BNL-NUREG-51812, Brookhaven National Laboratory (July 1984).
  • C. E. PETERSON, V. K. CHEXAL, W. H. LAYMAN, R. D. HENTZEN, and G. C. GOSE, “An Investigation of Decreasing Reactor Coolant Inventory as a Mechanism to Reduce Power During a Boiling Water Reactor Anticipated Transient Without Scram,” Nucl. Technol., 70, 74 (1985).
  • M. LEE and E.-C. WU, “A Long-Term MAAP 3.0B Analysis of a Severe Anticipated Transient Without Scram in a Boiling Water Reactor,” Nucl. Technol., 100, 39 (1992).
  • T. J. LIAW, C. PAN, G.-S. CHEN, and J.-K. HSIUE, “Analysis of a Main Steam Isolation Valve Closure Anticipated Transient Without Scram in a Boiling Water Reactor,” Nucl. Technol., 88, 227 (1989).
  • J. G. M. ANDERSON, L. B. CLAASSEN, S. S. DUA, and J. K. GARRETT, “Analysis of Anticipated Transients Without Scram in Severe BWR Accidents”, EPRI NP-5562, Electric Power Research Institute (Dec. 1987).
  • “General Description of a Boiling Water Reactor”, General Electric Company (May 1974).
  • “ADSIM Reference Manual”, Applied Dynamics International (Aug. 1988).

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