Momentum coupled transient thermal-hydraulic model for BWRs
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5686873
- General Electric Corp., San Jose, CA
None
- OSTI ID:
- 5686873
- 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
BWR thermal hydraulics
A momentum integral network method for thermal-hydraulic transient analysis
Reactor core transient analysis using coupled neutronics and thermal-hydraulic models
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5745813
A momentum integral network method for thermal-hydraulic transient analysis
Conference
·
Wed Jun 01 00:00:00 EDT 1983
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5510726
Reactor core transient analysis using coupled neutronics and thermal-hydraulic models
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6870751
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
PRESSURE DROP
REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
PRESSURE DROP
REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS