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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsAssessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU [Korea Nuclear Unit] No. 1 Plant (NUREG/IA-0030)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0030 (PDF 2.39 MB)Publication Information **Date Published:** April 1990 **Prepared by:** Bud-Dong Chung, Hho-Jung Kim Nuclear Safety Center Korea Advanced Energy Research Institute Young-Jin Lee 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) **Published by:** Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555 Availability Notice Abstract 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. 
      
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