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Title: Assessment of short through-wall circumferential cracks in pipes. Experiments and analysis: March 1990--December 1994

Abstract

This topical report summarizes the work performed for the Nuclear Regulatory Commission`s (NRC) research program entitled ``Short Cracks in Piping and Piping Welds`` that specifically focuses on pipes with short through-wall cracks. Previous NRC efforts, conducted under the Degraded Piping Program, focused on understanding the fracture behavior of larger cracks in piping and fundamental fracture mechanics developments necessary for this technology. This report gives details on: (1) material property determinations, (2) pipe fracture experiments, and (3) development, modification, and validation of fracture analysis methods. The material property data required to analyze the experimental results are included. These data were also implemented into the NRC`s PIFRAC database. Three pipe experiments with short through-wall cracks were conducted on large diameter pipe. Also, experiments were conducted on a large-diameter uncracked pipe and a pipe with a moderate-size through-wall crack. The analysis results reported here focus on simple predictive methods based on the J-Tearing theory as well as limit-load and ASME Section 11 analyses. Some of these methods were improved for short-crack-length predictions. The accuracy of the various methods was determined by comparisons with experimental results from this and other programs. 69 refs., 124 figs, 49 tabs.

Authors:
; ;  [1]
  1. Battelle, Columbus, OH (United States); and others
Publication Date:
Research Org.:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Battelle Memorial Inst., Columbus, OH (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
46619
Report Number(s):
NUREG/CR-6235; BMI-2179
ON: TI95010506; TRN: 95:011069
DOE Contract Number:  
FG02-90ER14135
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Apr 1995
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 36 MATERIALS SCIENCE; NUCLEAR POWER PLANTS; PIPES; CRACK PROPAGATION; CARBON STEELS; STAINLESS STEEL-316; STAINLESS STEEL-316L; FRACTURE PROPERTIES; TENSILE PROPERTIES; CHARPY TEST; WELDED JOINTS; LOSS OF COOLANT; EXPERIMENTAL DATA

Citation Formats

Brust, F W, Scott, P, and Rahman, S. Assessment of short through-wall circumferential cracks in pipes. Experiments and analysis: March 1990--December 1994. United States: N. p., 1995. Web. doi:10.2172/46619.
Brust, F W, Scott, P, & Rahman, S. Assessment of short through-wall circumferential cracks in pipes. Experiments and analysis: March 1990--December 1994. United States. https://doi.org/10.2172/46619
Brust, F W, Scott, P, and Rahman, S. 1995. "Assessment of short through-wall circumferential cracks in pipes. Experiments and analysis: March 1990--December 1994". United States. https://doi.org/10.2172/46619. https://www.osti.gov/servlets/purl/46619.
@article{osti_46619,
title = {Assessment of short through-wall circumferential cracks in pipes. Experiments and analysis: March 1990--December 1994},
author = {Brust, F W and Scott, P and Rahman, S},
abstractNote = {This topical report summarizes the work performed for the Nuclear Regulatory Commission`s (NRC) research program entitled ``Short Cracks in Piping and Piping Welds`` that specifically focuses on pipes with short through-wall cracks. Previous NRC efforts, conducted under the Degraded Piping Program, focused on understanding the fracture behavior of larger cracks in piping and fundamental fracture mechanics developments necessary for this technology. This report gives details on: (1) material property determinations, (2) pipe fracture experiments, and (3) development, modification, and validation of fracture analysis methods. The material property data required to analyze the experimental results are included. These data were also implemented into the NRC`s PIFRAC database. Three pipe experiments with short through-wall cracks were conducted on large diameter pipe. Also, experiments were conducted on a large-diameter uncracked pipe and a pipe with a moderate-size through-wall crack. The analysis results reported here focus on simple predictive methods based on the J-Tearing theory as well as limit-load and ASME Section 11 analyses. Some of these methods were improved for short-crack-length predictions. The accuracy of the various methods was determined by comparisons with experimental results from this and other programs. 69 refs., 124 figs, 49 tabs.},
doi = {10.2172/46619},
url = {https://www.osti.gov/biblio/46619}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Apr 01 00:00:00 EST 1995},
month = {Sat Apr 01 00:00:00 EST 1995}
}