COBRA/TRAC large-break LOCA calculations
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6894149
None
- Research Organization:
- Battelle-Pacific Northwest Laboratory, P.O. Box 999, Richland, WA 99352
- OSTI ID:
- 6894149
- Report Number(s):
- CONF-840614-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 46
- Country of Publication:
- United States
- Language:
- English
Similar Records
COBRA/TRAC simulation of a semiscale small-break LOCA
COBRA/TRAC simulation of a semiscale small break LOCA. [PWR]
COBRA/ TRAC simulation of the semiscale S-UT-5 small-break loss-of-coolant accident
Conference
·
Sat Oct 01 00:00:00 EDT 1983
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5159228
COBRA/TRAC simulation of a semiscale small break LOCA. [PWR]
Conference
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:5624402
COBRA/ TRAC simulation of the semiscale S-UT-5 small-break loss-of-coolant accident
Conference
·
Mon Dec 31 23:00:00 EST 1984
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5112232
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
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
THERMODYNAMICS
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
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
THERMODYNAMICS
WATER COOLED REACTORS
WATER MODERATED REACTORS