Dynamic simulation of a Westinghouse PWR four-loop plant during steam generator tube rupture event Public Deposited

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/7d278w67c

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  • This study addresses the application of a full reactor system computer code to simulate the reactor primary and secondary loop thermal hydraulics, plant control and protection systems during the steam generator tube rupture (SGTR) events. The Trojan nuclear plant which is owned and operated by the Portland General Electric (PGE) served as the basis for this computer simulation. The primary objective was to investigate the response a four-loop PWR to a steam generator tube rupture and the effect of various operator actions. To achieve this objective, several models were developed to simulate the behaviour of automatic control systems and the plant's operator actions. A lumped two-loop RETRAM model, which represents the actual four-loop PWR plant, had been developed previously and was used as a starting point. The involved control systems and control actions which play important roles in SGTR transient conditions are incorporated into the two-loop model by using the control system option of RETRAN. The predicted results show the rapid depressurization and level deviation, which characterize the SGTR event, in the pressurizer. The depressurization rate can be affected by operator actions such as increasing the charging flow rate or reducing the reactor power. The feedwater controller on the intact lumped triple-loop side functions normally and maintains the same water level, while on the ruptured one-loop side the water level significantly deviates from the normal level and causes a steam-flow/feed-flow mismatch alarm.
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