Degraded piping program: Phase II: Sixth program report, October 1986--September 1987
Description
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
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A15/MF A01 - US Govt. Printing Office; 1 as TI88009209.
Files
Additional details
Publishing Information
- Imprint Pagination
- 331 p.
- Report number
- NUREG/CR--4082-Vol.6
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20008715
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data, Progress Report
- Descriptors DEI
- AGING; BENDING; BWR TYPE REACTORS; CARBON STEELS; CRACKS; EXPERIMENTAL DATA; FINITE ELEMENT METHOD; FRACTURE MECHANICS; LEAKS; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; N CODES; NUCLEAR POWER PLANTS; PIPES; PROGRESS REPORT; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; RESEARCH PROGRAMS; STAINLESS STEELS; STRESSES; THERMAL DEGRADATION; US NRC; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COMPUTER CODES; COOLING SYSTEMS; DATA; DEFORMATION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- BMI--2120-Vol.6.