HFIR (High Flux Isotope Reactor) pressure vessel and structural components materials surveillance program: Supplement 1
Technical Report
·
OSTI ID:6096745
Extending the life of the HFIR vessel by the proposed 10 effective full-power years is contingent upon a continuation of the materials surveillance program and the application of hydrostatic proof testing. As a part of the surveillance program, Charpy V-notch (CVN) specimens of shell, weld and nozzle materials are installed adjacent to the inner surface of the vessel and are removed periodically for testing to determine the radiation-induced increase in the nil-ductility transition temperature. Hydro testing is conducted to prove that a critical combination of flaw size, stress and fracture toughness does not exist. Information from the materials surveillance program is used in a fracture mechanics analysis to confirm that the hydro-test pressure being applied is appropriate for the desired life extension of the vessel. This report specifies (1) the number, type, location and schedule for removal-testing of the CVN specimens for the continuing materials surveillance program, and (2) the procedures and test conditions for the hydro test.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6096745
- Report Number(s):
- ORNL/TM-1372/S1; ON: DE88001593
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
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220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
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CHARPY TEST
CHEMICAL REACTIONS
CONTAINERS
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ENRICHED URANIUM REACTORS
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IRRADIATION
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MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MECHANICAL TESTS
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
RADIATION FLUX
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
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TANK TYPE REACTORS
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THERMAL REACTORS
WATER COOLED REACTORS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
CHARPY TEST
CHEMICAL REACTIONS
CONTAINERS
CORROSION
CRACKS
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
HFIR REACTOR
IMPACT TESTS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MECHANICAL TESTS
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
RADIATION FLUX
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SERVICE LIFE
SURVEILLANCE
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS