Effectiveness of recovery techniques during steam generator tube rupture in the Semiscale Mod-2B facility

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5432948

Loomis, G G

Results are presented from an experimental investigation of recovery techniques commonly used during steam generator tube rupture transients. Recovery experiments were conducted in the Semiscale Mod-2B facility at typical pressurized water reactor (PWR) conditions (6 to 8 MPa, saturated). Recovery techniques found effective for loop pressure control and/or subcooling during a tube rupture included: unaffected loop secondary feed and steam using auxiliary feedwater and controlled atmospheric dump valve steam flow; primary feed and bleed using pressurizer power-operated relief valve operation along with safety injection (SI); and initiation or termination of SI. Phenomena associated with the recovery procedures included condensation, steam compression, mass redistribution, and natural circulation. Results are related to actual PWR transient experience at the Ginna nuclear generating plant. 5 refs., 8 figs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5432948
• Report Number(s): EGG-M-10385; CONF-850646-9; ON: TI85014571
• Country of Publication: United States
• Language: English

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