Improved TRAC quench front model. [PWR; BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5351331
None
- Research Organization:
- Los Alamos Scientific Lab., NM
- OSTI ID:
- 5351331
- Report Number(s):
- CONF-791103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
- Country of Publication:
- United States
- Language:
- English
Similar Records
Calculation of the CANON experiment using TRAC code. [PWR; BWR]
TRAC-P1A calculations of Edwards' blowdown experiment. [PWR; BWR]
Prediction of quench and rewet temperatures. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6595098
TRAC-P1A calculations of Edwards' blowdown experiment. [PWR; BWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5855370
Prediction of quench and rewet temperatures. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6615027
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS