Analysis of steam generator tube rupture transients with single failure

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6496674

Trambauer, K

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-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

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STEAM GENERATORS
TRANSIENTS
TUBES
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