An experimental validation of the guideline for inelastic design analysis through structural model tests
Creators
- 1. Nagasaki Research Laboratory, Mitsubishi Heavy Industries, Ltd., 5-717-1 Fukahori-machi, Nagasaki 851-0392 (Japan)
- 2. Mitsubishi Heavy Industries, Ltd. (Japan)
- 3. Japan Atomic Power Company (Japan)
- 4. Japan Atomic Energy Agency (Japan)
Description
In this paper, the inelastic analysis procedures recommended to use in the advanced elevated temperature structural design guide under development in Japan for the improved design of future fast breeder reactors were validated through the structural model tests and the evaluation of the experimental results by the inelastic analyses. First, a thermal fatigue test of a 316FR hollow cylinder with two longitudinal weldments was conducted under the condition of combined constant axial load and cyclic movement of axial temperature distribution, which simulated the loading condition near the free surface of coolant sodium in the main vessel of fast breeder reactors (FBRs). In the experiments, longitudinal and radial ratcheting deformation were measured and crack initiation life was also examined. Second, the inelastic analyses were carried out in accordance with the recommended procedure by using the measured results of oscillating temperature distribution. Finally, the results of inelastic analyses were compared with the experimental results and it was validated that the recommended practice gave a conservative result for the deformation and a good estimation of strain range for the fatigue life evaluation
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2006.09.021Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2006.09.021;
- PII
- S0029-5493(06)00544-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 2
- Journal Page Range
- p. 389-398
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39049068
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINERS; COOLANTS; CRACK PROPAGATION; CYLINDERS; DESIGN; EVALUATION; FBR TYPE REACTORS; RATCHETING; SIMULATION; SODIUM; STRAINS; STRUCTURAL MODELS; TEMPERATURE DISTRIBUTION; THERMAL FATIGUE; VALIDATION
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; DEFORMATION; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FATIGUE; MECHANICAL PROPERTIES; METALS; REACTORS; TESTING
Optional Information
- Copyright
- Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.