J-integral elastic plastic fracture mechanics evaluation of the stability of cracks in nuclear reactor pressure vessels
Contributions were made toward developing a new methodology to assess the stability of cracks in pressure vessels made from materials that exhibit a significant increase in toughness during the early increments of crack growth. It has a wide range of validity from linear elastic to fully plastic behavior.
- Research Organization:
- Washington Univ. Technology Associates, Inc., St. Louis, MO (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5164403
- Report Number(s):
- SAND-80-0688; ALO-86; WUTA-7972-04; TRN: 80-014661
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
POWER REACTORS
PRESSURE VESSELS
CRACKS
STEELS
FRACTURE PROPERTIES
PLASTICITY
STABILITY
ALLOYS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties
36 MATERIALS SCIENCE
POWER REACTORS
PRESSURE VESSELS
CRACKS
STEELS
FRACTURE PROPERTIES
PLASTICITY
STABILITY
ALLOYS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties