Cross flow characteristics in a three fuel assemblies

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

OSTI ID:22107849

Bae, J. H.; Euh, D. J.; Park, C. K.; Youn, Y. J.; Kwon, T. S. ^[1]

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1. Korea Atomic Energy Research Inst. KAERI, Yuseong P.O. Box 105, Daejeon 305-600 (Korea, Republic of)

To evaluate the reactor thermal margin of APR+, reactor core flow distribution including both axial and lateral directional hydraulic resistances of fuel assemblies should be known. 3-Ch cross flow test facility has been constructed with three full-size fuel assemblies to investigate the cross flow characteristics. Performance tests have been performed. The axial and lateral directional hydraulic resistances of fuel assemblies have been measured. The test results have been compared to the CFD calculation. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22107849
• 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; 11 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
42 ENGINEERING
FLUID MECHANICS
FUEL ASSEMBLIES
NUCLEAR POWER PLANTS
PERFORMANCE
PWR TYPE REACTORS
REACTOR CORES
TEST FACILITIES