Degraded piping program: Phase II: Sixth program report, October 1986--September 1987
Presented herein is an Annual Report of the US NRC's Degraded Piping Program---Phase II. This is the sixth program report on this program. Prior reports were semiannual reports. The intent of this program is to experimentally validate and enhance available analytical methods for evaluating the mechanical behavior of nuclear power plant piping containing circumferentially oriented defects. Fifty-seven pipe experiments have been conducted to date. These and approximately fifty additional pipe experiments from other programs have been analyzed. In the analytical effort, a screening criterion has been developed to show when the net-section-collapse analysis is valid. This shows that even though materials such as stainless steel can fail at less than net-section-collapse loads if the pipe diameter is sufficiently large. Numerous predictive J-estimation schemes have been evaluated and modified. A finite length surface-cracked pipe estimation scheme has also been developed and incorporated into a computer code called NRCPIPE. This code provides a convenient way of analyzing cracked pipe with a number of currently accepted analytical methods. Supporting research efforts involve investigating geometry effects on J-R curves, as well as characterizing the material properties for each pipe tested. The significance of all of the efforts to date relative to pipe fracture analyses and flaw assessment criteria are discussed.
- Research Organization:
- Battelle Columbus Div., OH (USA)
- OSTI ID:
- 6957577
- Report Number(s):
- NUREG/CR-4082-Vol.6; BMI-2120-Vol.6; ON: TI88009209
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
PIPES
FRACTURE MECHANICS
PWR TYPE REACTORS
US NRC
RESEARCH PROGRAMS
AGING
BENDING
CARBON STEELS
CRACKS
EXPERIMENTAL DATA
FINITE ELEMENT METHOD
LEAKS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
N CODES
NUCLEAR POWER PLANTS
PROGRESS REPORT
STAINLESS STEELS
STRESSES
THERMAL DEGRADATION
WELDED JOINTS
ALLOYS
CHROMIUM ALLOYS
COMPUTER CODES
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DATA
DOCUMENT TYPES
ENERGY SYSTEMS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUMERICAL DATA
NUMERICAL SOLUTION
POWER PLANTS
REACTOR COMPONENTS
REACTORS
STEELS
THERMAL POWER PLANTS
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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