Short cracks in piping and piping welds
- Battelle, Columbus, OH (USA)
This is the first 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. Additional efforts involve investigating phenomena discovered during the course of conducting the Degraded Piping program. These include the evaluation of the occurrence of unstable crack jumps in ferritic steels at LWR temperatures, and the occurrence of anisotropic fracture properties causing helical crack growth. Both of these phenomena may affect the safety margins implicit in LBB analyses. Other investigations deal with the fracture behavior of bi-metallic welds, and improvements in crack opening area analyses used in LBB. Since much of the work in this program was just beginning during this first reporting period and progress is limited, a complete statement of work for the whole program is provided in this report. 42 refs., 14 figs., 11 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Battelle, Columbus, OH (USA)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
- OSTI ID:
- 5895215
- Report Number(s):
- NUREG/CR-4599-Vol.1-No.1; BMI-2173-Vol.1-No.1; ON: TI91012463
- 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, October 1991--March 1992: Volume 2, No. 2
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PIPES
CRACKS
SEISMIC EFFECTS
WELDED JOINTS
PWR TYPE REACTORS
CRACK PROPAGATION
FRACTURE MECHANICS
MECHANICAL PROPERTIES
N CODES
PROGRESS REPORT
REACTOR MATERIALS
REACTOR SAFETY
RESEARCH PROGRAMS
STEELS
ALLOYS
COMPUTER CODES
DOCUMENT TYPES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MECHANICS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties