Transient CHF prediction by fluid modeling. [PWR and BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7136188
None
- Research Organization:
- Iowa State Univ., Ames
- OSTI ID:
- 7136188
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6612544
Prediction of critical heat flux during flow transients. [PWR; BWR]
Conference
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Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
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Prediction of CHF in rod bundles using round-tube CHF correlation. [PWR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5317122
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
BWR TYPE REACTORS
CRITICAL HEAT FLUX
HEAT FLUX
MATHEMATICAL MODELS
MOCKUP
PWR TYPE REACTORS
REACTORS
SIMULATION
STRUCTURAL MODELS
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
BWR TYPE REACTORS
CRITICAL HEAT FLUX
HEAT FLUX
MATHEMATICAL MODELS
MOCKUP
PWR TYPE REACTORS
REACTORS
SIMULATION
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS