SPACE code simulation of cold leg small break LOCA in the ATLAS integral test

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22107818

Kim, B. J.; Kim, H. T. ^[1]; Kim, J. ^[2]; Kim, K. D. ^[1]

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1. Thermal Hydraulics Safety Research Div., Korea Atomic Energy Research Inst., 1045 Daedeokdaero, Yuseong, Daejeon, 305-353 (Korea, Republic of)
2. Dept. of Mechanical System Design Engineering, Seoul National Univ. of Science and Technology, 232 Gongreung-Ro, Nowon-Gu, Seoul 139-743 (Korea, Republic of)

SPACE code is a system analysis code for pressurized water reactors. This code uses a two-fluid and three-field model. For a few years, intensive validations have been performed to secure the prediction accuracy of models and correlations for two-phase flow and heat transfer. Recently, the code version 1.0 was released. This study is to see how well SPACE code predicts thermal hydraulic phenomena of an integral effect test. The target experiment is a cold leg small break LOCA in the ATLAS facility, which has the same two-loop features as APR1400. Predicted parameters were compared with experimental observations. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22107818
• Resource Relation: Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 5 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICAL METHODS AND COMPUTING
ACCURACY
COMPUTER CODES
FLUIDS
FORECASTING
HEAT TRANSFER
LOSS OF COOLANT
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
SIMULATION
SYSTEMS ANALYSIS
THERMAL HYDRAULICS
TWO-PHASE FLOW
VALIDATION