Assessment Study of RELAP5/MOD2 Cycle 36.05 Based on the DOEL 4 Reactor Trip of November 22, 1985 (NUREG/IA–0051)
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Publication Information
Date Published: March 1992
Prepared by:
M. De Vlaminck, P. Deschutter, L. Vanhoenacker
TRACTEBEL
Avenue Ariane 7
B-1200 Brussels
Belgium
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 20555-0001
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Abstract
This report presents a code assessment study for RELAP-5 MOD-2/CYCLE 36.05 based on a plant transient that occured at the Belgian DOEL-4 nuclear power plant.
High level in steam generator G led to a turbine trip followed by reactor trip. This test was performed as part of the first cycle testingprogram on November 22th, 1985, and most important plant parameters were recorded on a Data Acquisition System (DAS).
The analysis by means of the frozen version of the RELAP-5 MOD-2/CYCLE 36.05 code was performed to qualify the plant input data deck for this plant and assess the code potential for simulating such transient. This work is performed by TRACTEBEL, which is the Architect-engineer for all Belgian nuclear power plants and a member of ICAP.
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