Comparison of containment leak-rate data analysis methods. [PWR and BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7341640
- Gilbert/Commonwealth, Jackson, MI
None
- OSTI ID:
- 7341640
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
Is eight hours of containment leak rate data sufficient. [PWR]
Value/impact comparison of alternate containment designs. [PWR, BWR]
Model for secondary containment pressure transient analysis. [PWR; BWR]
Conference
·
Mon Aug 01 00:00:00 EDT 1977
· Trans. Am. Nucl. Soc., Suppl.; (United States)
·
OSTI ID:7096097
Value/impact comparison of alternate containment designs. [PWR, BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5356907
Model for secondary containment pressure transient analysis. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6615000
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
CONTAINMENT
CONTAINMENT BUILDINGS
LEAKS
MONITORING
PWR TYPE REACTORS
RADIATION MONITORING
REACTORS
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
CONTAINMENT
CONTAINMENT BUILDINGS
LEAKS
MONITORING
PWR TYPE REACTORS
RADIATION MONITORING
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS