Effect of sleeves on quenching of a 4-rod bundle. [PWR; BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6877350
None
- Research Organization:
- Univ. of California, Los Angeles
- OSTI ID:
- 6877350
- Report Number(s):
- CONF-800607-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
- Country of Publication:
- United States
- Language:
- English
Similar Records
Study of uncovery transients in a 3 x 3 rod bundle. [BWR; PWR]
Effects of pressures and materials to the quenching of solids. [BWR, PWR]
BWR rod bundle benchmark problem
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6877354
Effects of pressures and materials to the quenching of solids. [BWR, PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5250016
BWR rod bundle benchmark problem
Conference
·
Tue Jun 01 00:00:00 EDT 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7351987
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
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MECHANICS
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
STRESSES
THERMAL STRESSES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MECHANICS
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
STRESSES
THERMAL STRESSES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS