Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU [Korea Nuclear Unit] No. 1 Plant (NUREG/IA-0030)
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Date Published: April 1990
Bud-Dong Chung, Hho-Jung Kim
Nuclear Safety Center
Korea Advanced Energy Research Institute
Department of Nuclear Engineering
Seoul National University
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
This report presents a code assessment study based on a real plant transient that occurred on June 9, 1981 at the KNU #1 ( Korea Nuclear Unit Number 1 ). KNU #1 is a two-loop Westinghouse PWR plant of 587 Mwe. The loss of offsite power transient occurred at the 77.5 X reactor power with 0.5 %/hr power ramp. The real plant data were collected from available on-line plant records and computer diagnostics.
The transient was simulated by RELAP5/MOD2/36.05 and the results were compared with the plant data to assess the code weaknesses and strengths. Some nodalizatlon studies were performed to contribute to developing a guideline for PWR nodalization for the transient analysis.