Best-estimate analysis of a small-break loss-of-coolant accident for a PWR plant

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6780227

Ragheb, M; Ikonomopoulos, A; Jones, B G ^[1]; Ho, S A; Endicott, R

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1. Univ. of Illinois, Urbana (United States)

This paper presents the results of a small-break loss-of-coolant accident transient analysis for the Salem Westinghouse four-loop pressurized water reactor (PWR). The analysis has been performed using the MOD2 version of the best-estimate code RELAP5 on a Cyber 932 under the NOS/VE operating system. This version of the code uses a nonhomogeneous, nonequilibrium, one-dimensional, two-phase flow model that is solved by a partially implicit numerical scheme. This effort is justified by the recent recognition by some nuclear utilities of the need to perform more realistic transient analyses using best-estimate models, while retaining the necessary conservatism of the evaluation models. It is believed that the improved computational capabilities of these analyses will increase the plants' availability and operational flexibility, as well as expand plant operating lifetimes.

• OSTI ID: 6780227
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
• Country of Publication: United States
• Language: English

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