RETRAN-02 Analysis of Ginna Nuclear Power Plant’s Steam Generator Tube Rupture Accident
to assess the capability of the RETRAN code to predict the response for this type of transient and
to illustrate a modeling technique by the development of a RETRAN data deck for the R. E. Ginna plant; the data deck was developed based on the available data and a generic Westinghouse design for a two-loop pressurized water reactor.
KeywordsSteam Generator Secondary Side Steam Generator Tube Tube Rupture Isolation Valve
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- (1).“NRC Report on the January 25, 1982, Steam Generator Tube Rupture at R. E. Ginna Nuclear Power Plant,” NUREG-0909, April 1982.Google Scholar
- (2).“Steam Generator Tube Rupture Incident at R. E. Ginna Nuclear Power Plant,” Docket No. 50-244, April 1982.Google Scholar
- (3).J. McFadden et al., “RETRAN-02: A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” Vols. 1-3, EPRI #NP-1850-CCM-5, Electric Power Research Institute, April 1981.Google Scholar
- (4).J. Chao, B. Chexal, W. Layman, D. Rautmann, C. Peterson, J. Atchison, and B. Hansen, “RETRAN-02 Analysis of a Steam Generator Tube Rupture Incident,” Conference Proceedings: Second International RETRAN Conference, EPRI NP-2494-SR, July 1982.Google Scholar
- (5).L. B. Marsh, “Evaluation of Steam Generator Tube Rupture Events,” NUREG-0651, March 1980.Google Scholar
- (6).W. G. Choe and Y. Matsui, “Ginna Accident Analysis by Using RETRAN-02 Computer Code,” Presented at the 1982 Fall Meeting of the Atomic Energy Society of Japan, October 1982.Google Scholar