Probabilistic analysis of PWR fuel rod behavior during a LOCA using the response surface method
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6672640
None
- Research Organization:
- KFZ Karlsruhe-Germany
- OSTI ID:
- 6672640
- Report Number(s):
- CONF-790519-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 31
- Country of Publication:
- United States
- Language:
- English
Similar Records
Probabilistic assssment of fuel rod ballooning in large-bundle LOCA experiments. [BWR, PWR]
Analysis of LOCA fuel rod behavior including azimuthal temperature distribution
Behavior of failed fuel rod during film boiling operation. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5355844
Analysis of LOCA fuel rod behavior including azimuthal temperature distribution
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5046651
Behavior of failed fuel rod during film boiling operation. [PWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5899097
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RISK ASSESSMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RISK ASSESSMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS