RELAP5 subcooled critical flow model verification

Conference · Fri Jan 01 00:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6954075

Petelin, S; Gortnar, O; Mavko, B ^[1]

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1. Institut Jozef Stefan, Ljubljana (Solomon Islands)

We discuss some results of the RELAP5 break modeling during the analysis of International Standard Problem 27 (ISP-27) performed on the BETHSY facility. This study deals with the discontinuity of the RELAP5 critical flow prediction in a strongly subcooled region. Such unrealistic behavior was observed during the pretest simulations of ISP-27. Based on the investigation, a RELAP5 code correction is suggested that ensures a more appropriate simulation of the critical discharge of strongly subcooled liquid.

• OSTI ID: 6954075
• Report Number(s): CONF-931160-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
CRITICAL FLOW
R CODES
VERIFICATION
ACCURACY
FLUID MECHANICS
LOSS OF COOLANT
SIMULATION
SUBCOOLING
ACCIDENTS
COMPUTER CODES
COOLING
FLUID FLOW
MECHANICS
REACTOR ACCIDENTS
420400* - Engineering- Heat Transfer & Fluid Flow