Local heat transfer coefficients in containments after a LOCA. [PWR; BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5351469
None
- Research Organization:
- Univ. of Illinois, Urbana
- OSTI ID:
- 5351469
- 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
Condensing heat transfer following a LOCA. [BWR, PWR]
Radioactive release following a LOCA with an initially breached containment. [PWR; BWR]
Analysis of containment heat transfer following LOCA
Conference
·
Wed Jun 01 00:00:00 EDT 1977
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7220996
Radioactive release following a LOCA with an initially breached containment. [PWR; BWR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5351465
Analysis of containment heat transfer following LOCA
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7328679
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
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CONTAINMENT
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ENGINEERED SAFETY SYSTEMS
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LOSS OF COOLANT
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REACTOR ACCIDENTS
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THERMAL STRESSES
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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
CONTAINMENT
CONTAINMENT SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
HEAT TRANSFER
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TEMPERATURE GRADIENTS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS