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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Results are presented for a steamline break analysis for a typical, two-loop, 2560 MW(t) pressurized water reactor. The calculations were performed using the IRT reactor system transient analysis code. Included are the analyses of steamline break transients assuming concurrent steam generator tube rupture (up to 30 steam generator tubes). Graphical and tabular results are presented.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Results are presented for a steamline break analysis for a typical, two-loop, 2560 MW(t) pressurized water reactor. The calculations were performed using the IRT reactor system transient analysis code. Included are the analyses of steamline break transients assuming concurrent steam generator tube rupture (up to 30 steam generator tubes). Graphical and tabular results are presented.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
A problem currently experienced in commercial operating pressurized water reactors (PWR) in the United States is the degradation of steam generator tubes. Safety questions have arisen concerning the effect of these degraded tubes rupturing during a postulated loss-of-coolant accident (LOCA). To determine the effect of a small number of tube ruptures on the behavior of a large PWR during a postulated LOCA, a series of computer simulations was performed. The primary concern of the study was to determine whether a small number (10 or less of steam generator tubes rupturing at the beginning surface temperatures. Additional reflood analyses were performed to determine the system behavior when from 10 to 60 tubes rupture at the beginning of core reflood. The FLOOD4 code was selected as being the most applicable code for use in this study after an extensive analysis of the capabilities of existing codes to perform simulations of a LOCA with concurrent steam generator tube ruptures. The results of the study indicate that the rupturing of 10 or less steam generator tubes in any of the steam generators during a 200% cold leg break will not result in a significant increase in the peak cladding temperature. However, because of the vaporization of the steam generator secondary water in the primary side of the steam generator, a significant increase in the core pressure occurs which retards the reflooding process.
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Author: Jukka T. Laaksonen
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Author: Faye H. Horn
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