Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

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

Similar Records

HFIR Pressure Vessel and Structural Components Materials Surveillance Program. Supplement 2
Technical Report · Sun Aug 01 00:00:00 EDT 1999 · OSTI ID:12446
Irradiation surveillance program as applied in Switzerland
Conference · Wed Dec 31 23:00:00 EST 1980 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) · OSTI ID:6187057
Current and advanced pressure vessel surveillance specimen evaluation techniques
Conference · Sun Dec 31 23:00:00 EST 1972 · Conf. Remote Syst. Technol., Proc., no. 21, pp. 86-90 · OSTI ID:4387596

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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