Published 1979
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Elastic-plastic-creep analysis of shells
Description
This paper presents the recent experience of a designer/fabricator of nuclear heat transport components in the area of elastic-plastic-creep analysis of shell-like structures. A brief historical perspective is first given to highlight the evolution leading to the present industry practice. The ASME elevated temperature design criteria will be discussed followed by examples of actual computations performed to support the design/analysis and fabrication of a breeder reactor component in which a substantial amount of elastic-plastic-creep analysis was performed. Mathematical challenges encountered by the design analyst in these problems will be highlighted. Developmental needs and future trends will then be given
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
10488159.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- CONF-790402--16
Conference
- Title
- Computational methods in nuclear engineering.
- Dates
- 23 - 25 Apr 1979.
- Place
- Williamsburg, VA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10488159
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; CREEP; HEAT EXCHANGERS; LMFBR TYPE REACTORS; SHELLS; STRESS ANALYSIS; THERMAL STRESSES
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; STRESSES