PCRV structural response verification. [HTGR]
Tendon loads, strain, and deflection data are analyzed for the purpose of validating structural analysis computer codes by comparison of observed vessel behavior with predicted PCRV structural response at Fort St. Vrain. On the basis of test data obtained during reactor rise to 70% power, the following observations on the overall structural response of the PCRV are made: the structural response of the vessel to pressure changes is essentially linear; the consistency exhibited in the concrete strain and deflection data obtained from the initial proof pressure and start-up tests indicates that no significant change in the PCRV structural stiffness has occurred during this period; the long-term tendon loads have been conservatively estimated in the PCRV design; and good correlations between analytical results and measured data verify the adequacy of the two-dimensional creep analysis code used to predict the time-dependent structural response of the FSV PCRV.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- EY-76-C-03-0167-065
- OSTI ID:
- 6441644
- Report Number(s):
- GA-A-15171
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
BUILDING MATERIALS
CONCRETES
CONTAINERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
PERFORMANCE
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTORS
STRAINS
STRESSES
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
BUILDING MATERIALS
CONCRETES
CONTAINERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MATERIALS
PERFORMANCE
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTORS
STRAINS
STRESSES