Short cracks in piping and piping welds
- Battelle, Columbus, OH (United States)
This is the second semiannual report of the US Nuclear Regulatory Commission's Short Cracks in Piping and Piping Welds research program. The program began in March 1990 and will extend for 4 years. The intent 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 in-service flaw evaluations. Only quasi-static loading rates are evaluated since the NRC's International Piping Integrity Research Group (IPIRG) program is evaluating the effects of seismic loading rates on cracked piping systems. Progress for through-wall-cracked pipe involved (1) conducting a 28-inch diameter stainless steel SAW and 4-inch diameter French TP316 experiments, (2) conducting a matrix of FEM analyses to determine GE/EPRI functions for short TWC pipe, (3) comparison of uncracked pipe maximum moments to various analyses and FEM solutions, (4) development of a J-estimation scheme that includes the strength of both the weld and base metals. Progress for surface-cracked pipe involved (1) conducting two experiments on 6-inch diameter pipe with d/t = 0.5 and {Theta}/{pi} = 0.25 cracks, (2) comparisons of the pipe experiments to Net-Section-Collapse predictions, and (3) modification of the SC.TNP and SC.TKP J-estimation schemes to include external surface cracks.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Battelle, Columbus, OH (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5460486
- Report Number(s):
- NUREG/CR-4599-Vol.1-No.2; BMI--2173-Vol.1-No.2; ON: TI92010715
- Country of Publication:
- United States
- Language:
- English
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Short Cracks in Piping and Piping Welds
Short cracks in piping and piping welds. Semiannual report, April 1992--September 1992: Volume 3, No. 1
Related Subjects
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
AGING
ALLOYS
CHEMICAL COMPOSITION
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
EVALUATION
FINITE ELEMENT METHOD
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL SOLUTION
PIPES
POWER PLANTS
PROGRESS REPORT
SEISMIC EFFECTS
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
THERMAL POWER PLANTS
WELDED JOINTS