Proposal of fatigue crack growth rate curve in air for nickel-base alloys used in BWR
- 1. Toshiba Corp., Power and Industrial Systems Research and Development Center, Yokohama, Kanagawa (Japan)
- 2. Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki (Japan)
- 3. Hitachi, Ltd., Hitachi Research Laboratory, Hitachi, Ibaraki (Japan)
- 4. Hokuriku Electric Power Co., Inc., Toyama (Japan)
Description
When the defects are detected in the nuclear components in Japan, structural integrity assessment should be performed for the technical judgment on continuous service based on the Rules on Fitness-for-Service for Nuclear Power Plants of the Japan Society of Mechanical Engineers Code (JSME FFS Code). Fatigue crack growth analysis is required when the cyclic loading would be applied for the components. Recently, fatigue crack growth rate curve in air environment for Nickel-base alloys weld metal used in BWR was proposed by the authors and it was adopted as a code case of JSME FFS Code to evaluate the embedded flaw. In this study, fatigue crack growth behavior for heat-affected zone (HAZ) of Nickel-base alloys in air was investigated. And a unified fatigue crack growth rate curve in air for HAZ and weld metal of Nickel-base alloys used in BWR was evaluated. As a result, it was found that the curve for weld metal could be applied as a curve for both HAZ and weld metal since moderately conservative assessment of fatigue crack growth rate of HAZ is possible by the curve for weld metal in the Paris region. And the threshold value of stress intensity far range (ΔKth) is determined to 3.0 MPa√m based on the fatigue crack growth rate of HAZ. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 79
- Journal Issue
- 806
- Journal Page Range
- p. 1550-1554
- ISSN
- 0387-5008
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 45080437
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; FATIGUE; HEAT AFFECTED ZONE; NICKEL BASE ALLOYS; NUCLEAR POWER PLANTS; STRESS INTENSITY FACTORS; WELDED JOINTS
- Descriptors DEC
- ALLOYS; ENRICHED URANIUM REACTORS; JOINTS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZONES
Optional Information
- Notes
- 5 refs., 4 figs., 3 tabs.