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Analysis of pressurized water reactor anticipated transient without scram transients with RETRAN-02

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5059536
; ;

This paper describes the analysis of a loss of feedwater (LOFW) ATWS on a U-tube PWR (pressurized water reactor). The capabilities of the RETRAN-02 code have been extended to allow it to perform pressurized water reactor anticipated transient without scram (ATWS) calculations. A loss-of-feedwater ATWS was performed with RETRAN-02 and compared with vendor calculations with excellent agreement. 2 refs.

Research Organization:
EPRI, Palo Alto, Calif, USA
OSTI ID:
5059536
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 54:3; ISSN NUTYB
Country of Publication:
United States
Language:
English

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