Published 1979 | Version v1
Report Open

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.

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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