Analytical modeling of transient two-phase flow. [PWR; BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5686928
None
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC
- OSTI ID:
- 5686928
- Report Number(s):
- CONF-790602-(Summ.)
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analytical model for transient gas flow in nuclear fuel rods. [BWR; PWR]
Theoretical foundation for the modeling of two-phase flow. [PWR; BWR]
Dynamic analysis of a drag-disk in transient two-phase flow. [PWR; BWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5899098
Theoretical foundation for the modeling of two-phase flow. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6594791
Dynamic analysis of a drag-disk in transient two-phase flow. [PWR; BWR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5260357
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
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
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
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS