Assessment of RELAP5/MOD2 computer code against the Net Load Trip Test data from Yong-Gwang, Unit 2
- Korea Electric Power Co., Taejeon (Korea, Republic of)
- Korea Inst. of Nuclear Safety, Taejeon (Korea, Republic of)
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.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Electric Power Co., Taejon (Korea, Republic of); Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 6503181
- Report Number(s):
- NUREG/IA-0092; ON: TI93016089
- Country of Publication:
- United States
- Language:
- English
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ASIA
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL SYSTEMS
COOLING SYSTEMS
DEVELOPING COUNTRIES
ENERGY LOSSES
ENRICHED URANIUM REACTORS
LOSSES
OPERATION
POWER LOSSES
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REPUBLIC OF KOREA
SAFETY
SENSITIVITY ANALYSIS
SIMULATION
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS