Assessment of RELAP5/MOD2 Computer Code Against the Net Load Trip Test Data From Yong–Gwang, Unit 2 (NUREG/IA-0092)
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Date Published: June 1993
Namsung Arne, Sungjae Cho/KEPC
Sang Hoon Lee/KINS
Korea Electric Power Co.
17-15, Yongjeon-Dong, Dong-Gu
Korea Institute of Nuclear Safety
P.O. Box 16, Daeduck Danji
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
The results of the RELAP5/MOD2 computer code simulation for the 100 % Net Load Trip Test in Yong-Gwang Unit 2 are analyzed here and compared with the plant operation data. The control systems for the control rod, feedwater, steam generator level, steam dump, pressurizer level and pressure are modeled to be functioned automatically until the power level decreases below 30 % nuclear power. A sensitivity study on control rod worth was carried out and it was found that variable rod worth should be used to achieve good prediction of neutron power. The results obtained from RELAP5/MOD2 simulation agree well with the plant operating data and it can be concluded that this code has the capability in analyzing the transient of this type in a best estimate means.