Assessment of RELAP5/MOD3 Version 5m5 using inadvertent safety injection incident data of Kori Unit 3 Plant

Technical Report · Sat May 01 00:00:00 EDT 1993

OSTI ID:10164148

Kim, K T; Chung, B D; Kim, I G; Kim, H J ^[1]

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1. Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)

This report discusses an inadvertent safety injection incident which occurred at Kori Unit 3 in September 6, 1990 was analyzed using the RELAP5/MOD3 code. The event was initiated by a closure of main feedwater control valve of one of three steam generators. High pressure safety injection system was actuated by the low pressure signal of main steam line. The actual sequence of plant transient with the proper estimations of operator actions was investigated in the present calculation. The asymmetric loop behaviors of the plant was also considered by nodalizing the loops of the plant into three. The calculational results are compared with the plant transient data. It is shown that the overall plant transient depends strongly on the auxiliary feedwater flowrate controlled by the operator and that the code gives an acceptable prediction of the plant behavior with the proper assumptions of the operator actions. The results also show that the solidification of pressurizer is not occurred and the liquid-vapor mixture does not flow out through pressurizer PORV. The behavior of primary pressure during pressurizer PORV actuation is poorly predicted because the actual behavior of pressurizer PORV could not be modelled in the present simulation.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10164148
• Report Number(s): NUREG/IA-0105; ON: TI93014892; TRN: 93:016226
• Resource Relation: Other Information: PBD: May 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
PWR TYPE REACTORS
TRANSIENTS
HIGH PRESSURE COOLANT INJECTION
REACTOR COOLING SYSTEMS
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
FLUID FLOW
FLOW RATE
R CODES
INTERNATIONAL AGREEMENTS
TESTING
VALVES
PRESSURIZERS
COMPUTERIZED SIMULATION
220900
210200
990200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS