Analysis of LOFT large-break experiments L2-3 and L2-5 using RELAP5/MOD1
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5186337
None
- Research Organization:
- EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, ID 83415
- OSTI ID:
- 5186337
- Report Number(s):
- CONF-831047-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
- Country of Publication:
- United States
- Language:
- English
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Analysis of LOFT large-break tests L2-3 and L2-5 using the TRAC-PD2/MOD1
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·
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OSTI ID:5692959
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMODYNAMICS
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
THERMODYNAMICS
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS