Assessment of RELAP5/MOD2 Cycle 36. 04 with LOFT large break LOCE L2-3

Technical Report · Wed Apr 01 04:00:00 EST 1992

OSTI ID:5459560

Bang, Y S; Kim, H J ^[1]; Kim, S H ^[2]

---

1. Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
2. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

The LOFT LOCE L2-3 was simulated using the RELAP5/MOD2 Cycle 36.04 code to assess its capability to predict the thermal-hydraulic phenomena in LBLOCA of the PWR. The reactor vessel was simulated with two core channels and split downcomer modelling for a base case calculation using the frozen code. From the results of the base case calculation, deficiencies of the critical flow model and the CHF correlation at high flow rate were identified, and the severeness of the rewetting criteria were also found. Additional calculation using an updated version of RELAP5/MOD2 Cycle 36.04 including modifications of the rewet criteria shows a substantial improvement in the core thermal response.

• 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: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 5459560
• Report Number(s): NUREG/IA-0070; ON: TI92013437
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EVALUATION
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS