Condensation heat transfer test results for boiling systems with elevated heat exchanger configuration

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5854104

Coffield, R D; Schmidt, J E ^[1]

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1. Westinghouse Electric Corp., Madison, PA (United States)

This paper describes analyses and experiments that have been performed for a low-pressure heavy-water reactor design to help characterize shutdown heat removal through condensation heat transfer in the primary heat exchangers (PHXs) under loss-of-coolant accident (LOCA) conditions. This is one of many passive safety features that are dedicated to the mitigation of LOCA damage. The design combines the heat exchanger condensation phenomena with natural circulation system flows to provide an effective means of passively removing decay heat through the secondary system. This paper focuses on the inherent heat removal capability in the PHXs via condensation in the presence of steam/air mixtures (condensable/noncondensable gases).

• OSTI ID: 5854104
• Report Number(s): CONF-910603-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HEAVY WATER COOLED REACTORS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
AFTER-HEAT REMOVAL
BOILING
ENGINEERED SAFETY SYSTEMS
HEAT EXCHANGERS
HELIUM
LEAKS
MITIGATION
NATURAL CONVECTION
PIPES
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR ACCIDENTS
RHR SYSTEMS
SECONDARY COOLANT CIRCUITS
ACCIDENTS
CONVECTION
COOLING SYSTEMS
ELEMENTS
ENERGY TRANSFER
FLUID MECHANICS
FLUIDS
GASES
MASS TRANSFER
MECHANICS
NONMETALS
PHASE TRANSFORMATIONS
RARE GASES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated