Dynamic fracture analysis of HSST crack run-arrest experiments with nonisothermal wide plates
Conference
·
OSTI ID:6067934
Dynamic fracture analysis results from Heavy-Section Steel Technology (HSST) wide-plate crack-arrest tests are summarized. These tests relate to assessing nuclear reactor pressure vessel integrity under pressurized-thermal-shock (PTS) conditions. Computed results for five tests are compared with measurements of strain versus time, crack propagation speed, and the arrest location. Crack arrest toughness values determined by various analytical methods are compiled for test temperatures that range from mid-transition into the Charpy upper-shelf region for the test material.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6067934
- Report Number(s):
- CONF-860585-2; ON: TI86007868
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACKS
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PRESSURE VESSELS
STEELS
TESTING
THERMAL POWER PLANTS
THERMAL SHOCK
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACKS
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PRESSURE VESSELS
STEELS
TESTING
THERMAL POWER PLANTS
THERMAL SHOCK