Elastodynamic fracture analyses of large crack-arrest experiments
Conference
·
OSTI ID:6496376
Results obtained to date show that the essence of the run-arrest events, including dynamic behavior, is being modeled. Refined meshes and optimum solution algorithms are important parameters in elastodynamic analysis programs to give sufficient resolution to the geometric and time-dependent aspects of fracture analyses. Further refinements in quantitative representation of material parameters and the inclusion of rate dependence through viscoplastic modeling is expected to give an even more accurate basis for assessing the fracture behavior of reactor pressure vessels under PTS and other off-normal loading conditions.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6496376
- Report Number(s):
- CONF-8510173-13; ON: TI86002455
- Resource Relation:
- Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
- 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
PRESSURE VESSELS
CRACK PROPAGATION
THERMAL SHOCK
FRACTURE MECHANICS
PLATES
STEEL-ASTM-A533-B
ALLOYS
CARBON STEELS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICS
STEELS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESSURE VESSELS
CRACK PROPAGATION
THERMAL SHOCK
FRACTURE MECHANICS
PLATES
STEEL-ASTM-A533-B
ALLOYS
CARBON STEELS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICS
STEELS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled