Analysis of the RCS over cooling issue of a Westinghouse four-loop vintage plant using RELAP5/MOD3

Conference · Sat Dec 31 04:00:00 EST 1994

OSTI ID:100671

O`Dea, M E; Ho, S A; Wang, W; Ransom, V ^[1]

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1. Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering

Reactor Cooling System transient over cooling phenomena that have occurred following turbine trips in Westinghouse four-loop plants are discussed in the light of analytical results that have been obtained using a plant-specific RELAP5/MOD3 model. The model that has been developed and used for this study includes necessary control systems and balance of plant components. The model is based on a currently operating Westinghouse four-loop pressurized water reactor which permits a comparison of code predictions with actual plant data. The transients that were studied occurred as a result of turbine trips. During the trips, the units experienced over cooling of the reactor core. In order to determine the root cause of the over cooling, a series of parametric RELAP5/MOD3 analyses were performed. The significant results from these analyses are presented in this paper. The RELAP5/MOD3 thermal hydraulic analysis code, developed for the United States Nuclear Regulatory Commission by the Idaho National Engineering Laboratory, was used for this work.

• OSTI ID: 100671
• Report Number(s): CONF-941142--; ISBN 0-7918-1433-5
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTERIZED SIMULATION
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
R CODES
TRANSIENTS