Study on unstable ductile fracture of reactor primary piping, (1)
- 1. Tokyo Univ. (Japan). Faculty of Engineering
Description
Small cracks have been found in the austenitic stainless steel pipings for BWRs, and it was judged that these were originated from the stress corrosion cracking in welding heat-affected zones. These cracks were detected before the fracture of pipings occurs. In order to confirm that leak before break always materializes, it is necessary to analyze the behavior of crack development in piping materials, especially its stability. The 304 stainless steel used for the cooling pipes does not cause brittle fracture, and the development of cracks in it is stable, but there is some possibility to become unstable because the piping systems themselves for nuclear reactors have compliance. In this study, a plate with a center crack was analyzed before treating the problem of pipings. On the basis of the result of low compliance tensile test on the test pieces with center penetrating slit made of 304 stainless steel, the J-R curve was made. Next, the starting point of unstable development by high compliance test was estimated according to the tearing instability criterion. The basic concept of the analysis of unstable ductile fracture, the outline of the experiment, the analysis and their comparison are described. (Kako, I.)
Additional details
Additional titles
- Subtitle (English)
- Plate with center crack under tension
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 48
- Journal Issue
- 427
- Series
- Nippon Kikai Gakkai Ronbunshu, A Hen.
- Journal Page Range
- 267-274
- ISSN
- 0387-5008
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 14796316
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANALYTICAL SOLUTION; CRACK PROPAGATION; CRACKS; FINITE ELEMENT METHOD; NOTCHES; PLATES; PRIMARY COOLANT CIRCUITS; RUPTURES; STAINLESS STEEL-304; STRESSES; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; FAILURES; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; STAINLESS STEELS; STEELS; TRANSITION ELEMENT ALLOYS