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Chung, Bud-Dong; Kim, Hho-Jung
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Korea Atomic Energy Research Inst., Daeduk (Republic of Korea); Seoul National Univ. (Republic of Korea)1990
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Korea Atomic Energy Research Inst., Daeduk (Republic of Korea); Seoul National Univ. (Republic of Korea)1990
AbstractAbstract
[en] This report presents a code assessment study based on a real plant transient that occurred on June 9, 1981 at the KNU number-sign 1 (Korea Nuclear Unit Number 1). KNU number-sign 1 is a two-loop Westinghouse PWR plant of 587 Mwe. The loss of offsite power transient occurred at the 77.5% 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 nodalization studies were performed to contribute to developing a guideline for PWR nodalization for the transient analysis. 5 refs., 18 figs., 3 tabs
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Apr 1990; 98 p; NTIS, PC A05/MF A01 - GPO as TI90009898; OSTI; INIS
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