Analysis of steam generator tube rupture transients with single failure
The Gesellschaft fuer Reaktorsicherheit is engaged in the collection and evaluation of light water reactor operating experience as well as analyses for the risk study of the pressurized water reactor (PWR). Within these activities, thermohydraulic calculations have been performed to show the influence of different boundary conditions and disturbances on the steam generator tube rupture (SGTR) transients. The analyses of these calculations have focused on the measures and systems needed to cope with an SGTR. The reference plant for this analysis is a 1300-MW(e) PWR of Kraftwerk Union design with four loops, each containing a U-tube steam generator (SG) and a reactor cooling pump (RCP). The thermal-hydraulic code DRUFAN-02 was used for the transient calculations.
- Research Organization:
- Gesellschaft fuer Reaktorsicherheit Forschungsgelaende, Garching, West Germany
- OSTI ID:
- 6496674
- Report Number(s):
- CONF-860610-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 52; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
Nonboiling Water Cooled
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220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CODES
COOLING SYSTEMS
D CODES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
MECHANICS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
RUPTURES
SAFETY
STEAM GENERATORS
TRANSIENTS
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS