Short cracks in piping and piping welds
Technical Report
·
OSTI ID:7147015
- Battelle, Columbus, OH (United States)
This is the third semiannual report of the US Nuclear Regulatory Commission's Short Cracks in Piping and Piping Welds research program. This 4-year program began in March 1990. The overall objective of this program is to verify and improve fracture analyses for circumferentially cracked large-diameter nuclear piping with crack sizes typically used in leak-before-break analyses or inservice flaw evaluations.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Battelle, Columbus, OH (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 7147015
- Report Number(s):
- NUREG/CR-4599-Vol.2-No.1; BMI-2173-Vol.2-No.1; ON: TI92041268
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
NUCLEAR POWER PLANTS
PIPES
CRACKS
WELDED JOINTS
CRACK PROPAGATION
ELASTICITY
FRACTURE MECHANICS
INTEGRALS
PLASTICITY
PROGRESS REPORT
STEELS
ALLOYS
DOCUMENT TYPES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
TENSILE PROPERTIES
THERMAL POWER PLANTS
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties
36 MATERIALS SCIENCE
NUCLEAR POWER PLANTS
PIPES
CRACKS
WELDED JOINTS
CRACK PROPAGATION
ELASTICITY
FRACTURE MECHANICS
INTEGRALS
PLASTICITY
PROGRESS REPORT
STEELS
ALLOYS
DOCUMENT TYPES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
TENSILE PROPERTIES
THERMAL POWER PLANTS
220200* - Nuclear Reactor Technology- Components & Accessories
360103 - Metals & Alloys- Mechanical Properties