RELAP5 assessment of noncondensable test data for passive cooling applications
Conference
·
OSTI ID:6934104
Condensation heat transfer in the presence of noncondensable (NC) gases is of concern in the design of passive heat removal systems for a number of recently proposed advanced reactor designs. In general, the presence of NCs will degrade the efficiency of such passive heat removal systems and, in some cases, induce unstable flow patterns. As part of a research effort to better understand passive heat removal dynamics, a series of numerical steady-state simulations in the presence of NCs were performed to evalutate RELAP5/MOD3 against test data. This assessment was made using data from the University of California, Berkeley (UCB) natural circulation loop test facility. For fine enough nodalization in the condenser region, the RELAP5/MOD3 simulations generally captured the same phenomena as observed in the tests.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6934104
- Report Number(s):
- EGG-M-92391; CONF-921102--23; ON: DE93001967
- Country of Publication:
- United States
- Language:
- English
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RELAP5 assessment of noncondensable test data for passive cooling applications
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RELAP5/MOD3 simulation of steam condensation in the presence of noncondensible gases under natural circulation conditions
Conference
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Thu Oct 01 00:00:00 EDT 1992
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OSTI ID:10190134
RELAP5 assessment of noncondensable test data for passive cooling applications
Conference
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Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
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OSTI ID:6673003
RELAP5/MOD3 simulation of steam condensation in the presence of noncondensible gases under natural circulation conditions
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6912539
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONDENSATES
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONDENSATES
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS