Grouted support plates in reactor buildings at the Savannah River Site: Field investigation, tests, and seismic evaluation
Conference
·
OSTI ID:7239069
The Westinghouse Savannah River Company (WSRC) conducted a seismic evaluation of the grouted support plates in the reactor buildings at the Savannah River Site (SRS) in response to issues raised from an earlier analysis. Researchers conducted the tests in a reactor building that was no longer in use and transferred the results to other reactor buildings. This paper discusses tests, results, analysis, and modifications made to achieve seismic qualification. 4 refs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 7239069
- Report Number(s):
- WSRC-MS-91-354; CONF-9110122-28; ON: DE92015889
- Resource Relation:
- Conference: Natural phenomena hazards mitigation conference, St. Louis, MO (United States), 15-18 Oct 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR COOLING SYSTEMS
SEISMIC EFFECTS
SPECIAL PRODUCTION REACTORS
CONCRETES
FIELD TESTS
HEAT TRANSFER
HYDRAULICS
INVESTIGATIONS
REACTOR SAFETY
SAVANNAH RIVER PLANT
STEELS
SUPPORTS
TESTING
ADMINISTRATIVE PROCEDURES
ALLOYS
BUILDING MATERIALS
COOLING SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL STRUCTURES
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR COOLING SYSTEMS
SEISMIC EFFECTS
SPECIAL PRODUCTION REACTORS
CONCRETES
FIELD TESTS
HEAT TRANSFER
HYDRAULICS
INVESTIGATIONS
REACTOR SAFETY
SAVANNAH RIVER PLANT
STEELS
SUPPORTS
TESTING
ADMINISTRATIVE PROCEDURES
ALLOYS
BUILDING MATERIALS
COOLING SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL STRUCTURES
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors