Published 1986 | Version v1
Journal article

Analysis of steam generator tube rupture transients with single failure

Creators

  • 1. Gesellschaft fuer Reaktorsicherheit Forschungsgelaende, Garching, West Germany

Description

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

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
52
Series
Trans. Am. Nucl. Soc.
Journal Page Range
587-588
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
15-20 Jun 1986.
Place
Reno, NV (USA).

Optional Information

Secondary number(s)
CONF-860610--.