Effect of fins and repeated-rib roughness on the performance characteristics of a reactor vessel air cooling system for LMFBR shutdown heat removal

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6883032

Cheung, F B; Chawla, T C; Pedersen, D R; Tessier, J H; Webb, R L

The use of a totally passive cooling system for shutdown heat removal that rejects heat from the reactor vessel by radiation to the guard vessel and from the guard vessel to a circulating air stream driven by natural convection is a key feature of the US Department of Energy's liquid-metal reactor advanced design study concepts. General Electric refers to the system as the Reactor Vessel Auxiliary Cooling System (RVACS) and Rockwell International as the Reactor Auxiliary Cooling System (RACS). The circulating air stream is contained in the annular passage formed with guard vessel wall and the duct wall surrounding the guard vessel. Specifically, the RVACS/RACS is designed to assure adequate cooling of the reactor vessel under abnormal operational conditions associated with loss of heat removal through the normal heat transport path via the steam generator system or the DRACS, if available. To enhance the heat transfer, longitudinal radial fins or repeated ribs can be attached to the duct wall and/or the guard vessel. The purpose of the present paper is to summarize the status of the analytical work on the development of an optimum design configuration for the RVACS/RACS.

• Research Organization: Pennsylvania State Univ., University Park
• OSTI ID: 6883032
• Report Number(s): CONF-860610-; TRN: 87-016374
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
AFTER-HEAT REMOVAL
REACTOR COOLING SYSTEMS
REACTOR SAFETY
AIR
DESIGN
FLUID FLOW
HEAT TRANSFER
LOSS OF FLOW
NATURAL CONVECTION
REACTOR SHUTDOWN
REACTOR VESSELS
TRANSIENTS
US DOE
ACCIDENTS
BREEDER REACTORS
CONTAINERS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
GASES
LIQUID METAL COOLED REACTORS
MASS TRANSFER
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
SHUTDOWNS
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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