Published 1993
| Version v1
Book
Low cycle fatigue crack growth and ductile fracture under dynamic/cyclic loadings for Japanese carbon steel piping: Part II--Analytical study
Creators
- 1. Central Research Inst. of Electric Power Industry, Tokyo (Japan). Fast Breeder Reactor Dept.
- 2. Hitachi Ltd., Ibaraki (Japan). Mechanical Engineering Research Lab.
- 3. Hitachi Ltd., Ibaraki (Japan). Dept. of Nuclear Engineering
Description
Dynamic fracture behavior of circumferentially cracked pipe is important to evaluate the structural integrity of nuclear piping from the view point of leak-before-break concept under seismic conditions. Fracture tests were conducted for Japanese carbon steel (STS42) pipes which were subjected to cyclic or dynamic monotonic loading. This paper describes the analytical studies for these pipe tests. J-integral approach was applied to evaluate the cyclic crack growth. A new equation for calculating ΔJ for a circumferentially throughwall cracked pipe subjected to bending was proposed. The effects of dynamic or cyclic loading on pipe fracture were also investigated
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0993-5
- Imprint Title
- Creep, fatigue, flaw evaluation, and leak-before-break assessment
- Imprint Pagination
- 301 p.
- Journal Page Range
- p. 175-182.
Conference
- Title
- 1993 pressure vessel and piping conference.
- Dates
- 25-29 Jul 1993.
- Place
- Denver, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25025809
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; CARBON STEELS; CRACK PROPAGATION; DEFECTS; DYNAMIC LOADS; EARTHQUAKES; FRACTURE MECHANICS; MESH GENERATION; NUCLEAR POWER PLANTS; PIPES; PLASTICITY; REACTOR COOLING SYSTEMS; SEISMIC EFFECTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; DEFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SEISMIC EVENTS; STEELS; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-930702--Vol.266.