Ice basket stress analysis: D. C. Cook Nuclear Power Plant

Technical Report · Tue Mar 01 00:00:00 EST 1977

OSTI ID:7304409

A series of full-scale Ice Condenser blowdown tests performed in the Waltz Mill Ice Condenser Blowdown Facility, as initiated in 1973 and reported in WCAP-8282, demonstrated that optimized heat transfer performance of the ice baskets was achieved by enlarging the mesh opening size of the perforated metal forming the basket from /sup 1///sub 2/ inch by /sup 1///sub 2/ inch to 1 inch by 1 inch. This increase in mesh opening size represents the only modification to the basket cylinders. Overall dimensions, material selection and thickness, and percentage open area remain unchanged. Detail changes to the complete assembly included modifying the basket couplings to minimize the localized reduction in diameter within the basket, and increasing the flow area at the flat bottom end of the basket column. This report documents the additional analyses and tests that have been performed to re-qualify the design. The ice baskets, as documented in this report, are analyzed and tested for structural loads which envelop the qualification conditions for the D. C. Cook Nuclear Power Plant.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• OSTI ID: 7304409
• Report Number(s): WCAP-8887; TRN: 77-013912
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COOK-1 REACTOR
ICE CONDENSERS
COOK-2 REACTOR
CONTAINMENT SYSTEMS
HEAT TRANSFER
PERFORMANCE TESTING
CONDENSERS
CONTAINMENT
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STEAM CONDENSERS
TESTING
VAPOR CONDENSERS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled