Study on natural convection capability of liquid gallium for passive decay heat removal system (PDHRS)

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

OSTI ID:22105977

Kang, S. ^[1]; Ha, K. S. ^[2]; Lee, S. W.; Park, S. D.; Kim, S. M.; Seo, H.; Kim, J. H.; Bang, I. C. ^[1]

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1. Ulsan National Inst. of Science and Technology UNIST, 100 Banyeon-ri, Eonyang-eup, Ulju-gun, Ulasn Metropolitan City 689-798 (Korea, Republic of)
2. Korea Atomic Energy Research Inst. KAERI, Deokjin-dong, Yuseong-gu, Daejeon, 305-600 (Korea, Republic of)

The safety issues of the SFRs are important due to the fact that it uses sodium as a nuclear coolant, reacting vigorously with water and air. For that reason, there are efforts to seek for alternative candidates of liquid metal coolants having excellent heat transfer property and to adopt improved safety features to the SFR concepts. This study considers gallium as alternative liquid metal coolant applicable to safety features in terms of chemical activity issue of the sodium and aims to experimentally investigate the natural convection capability of gallium as a feasibility study for the development of gallium-based passive safety features in SFRs. In this paper, the design and construction of the liquid gallium natural convection loop were carried out. The experimental results of heat transfer coefficient of liquid gallium resulting in heat removal {approx}2.53 kW were compared with existing correlations and they were much lower than the correlations. To comparison of the experimental data with computer code analysis, gallium property code was developed for employing MARS-LMR (Korea version of RELAP) based on liquid gallium as working fluid. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22105977
• 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; 27 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

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
AFTER-HEAT REMOVAL
AIR
COMPARATIVE EVALUATIONS
EXPERIMENTAL DATA
FAST REACTORS
FEASIBILITY STUDIES
GALLIUM
LIQUID METALS
M CODES
NATURAL CONVECTION
REACTOR SAFETY
SODIUM
THERMAL HYDRAULICS
THERMODYNAMIC ACTIVITY
THERMODYNAMIC PROPERTIES
WATER
WORKING FLUIDS