RELAP5/MOD2 Assessment, OECD-LOFT Small Break Experiment LP-SB-03 (NUREG/IA-0018)
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Date Published: April 1990
Paul Scherrer Institute
CH-5303 Wurenlingen, Switzerland
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
An analysis of the experimental results and oost-test calculations using RELAP5/MOD2 carried out for OECD-LOFT small break experiment LP-SB-3 are presented. Experiment LP-SB-3 was conducted on March 5, 1984 in the.Loss-of -Fluid Test (LOFT) facility located at the Idaho National Engineering Laboratory (INEL). The experiment simulated a small cold leg break, with concurrent loss of high pressure injection system, and cooldown and recovery by feed and bleed of the steam generator secondary side and accumulator injection, respectively.
The analysis was under taken as a part of a program at EIR aimed at developing experience in using the latest generation of best estimate Loss of Coolant Accident (LOCA) analysis computer codes, and to improve understanding of Small Break LOCA transients and as well as a part of a program aimed at assessing the RELAP5/MOD2 code. The latest available version (Cycle 33 to 36.1) of the code was used. The particular test selected for the analysis included several phenomena potentially relevant to any PWR plant operating in Switzerland.
This report documents a short post-test analysis of the experiment emphasizing the results of additional analysis prerformed during the course of this task. RELAPS/MOD2 input model and results of the post-test calculation are documented. Included in the report is the results of a sensitivity analysis which show the predicted thermal-hydraulic response to a different input model.