Selected plant transients and steam generator tube rupture with steamline break utilizing the IRT code. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5247576
- Brookhaven National Lab., Upton, NY
None
- OSTI ID:
- 5247576
- 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
PWR steamline break analysis assuming concurrent steam generator tube rupture
Steam generator tube rupture effects on a LOCA. [PWR]
Analysis of steam-line-break-induced steam generator tube rupture
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5025979
Steam generator tube rupture effects on a LOCA. [PWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5855318
Analysis of steam-line-break-induced steam generator tube rupture
Conference
·
Wed Dec 31 23:00:00 EST 1980
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6826897
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
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
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
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS