Assessment of RELAP5/MOD2 computer code against the Net Load Trip Test data from Yong-Gwang, Unit 2

Technical Report · Tue Jun 01 04:00:00 EDT 1993

OSTI ID:10165457

Arne, N; Cho, S ^[1]; Lee, S H ^[2]

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1. Korea Electric Power Co., Taejeon (KR)
2. Korea Inst. of Nuclear Safety, Taejeon (KR)

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 Corp. (KEPCO), Taejon (Korea, Republic of); Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10165457
• Report Number(s): NUREG/IA--0092; ON: TI93016089
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTERIZED SIMULATION
MATHEMATICS AND COMPUTERS
POWER LOSSES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REPUBLIC OF KOREA
SENSITIVITY ANALYSIS
TRANSIENTS