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A request has been made to the ASME Boiler and Pressure Vessel Committee that 6061-T6 aluminum be approved for use in the construction of Class 1 welded nuclear vessels so it can be used for the pressure vessel of the Advanced Neutron Source research reactor. Fatigue design curves with and without mean stress effects have been proposed. A knock-down factor of two is applied to the design curve for evaluation of welds. The basis of the curves is explained. The fatigue design curves are compared to fatigue data from base metal and weldments.
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| Authors: |
Yahr, G.T.
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| Publication Date: | 1993 Jun 01 |
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| OSTI Identifier: | OSTI ID: 10157028; Legacy ID: DE93011849 |
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| Report Number(s): | CONF-930702--14 |
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| DOE Contract Number: | AC05-84OR21400 |
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| Resource Type: | Conference/Event |
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| Resource Relation: | 1993 American Society of Mechanical Engineers (ASME) pressure vessel and piping conference,Denver, CO (United States),25-29 Jul 1993; Other Information: PBD: [1993] |
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| Research Org: | Oak Ridge National Lab., TN (United States) |
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| Sponsoring Org: | USDOE, Washington, DC (United States) |
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| Country of Publication: | United States |
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| Language: | English |
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| Format: | Size: 14 p. |
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| Other Number(s): | Other: ON: DE93011849 |
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| Specific Type: | Technical Report |
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| Subject: | 36 MATERIALS SCIENCE; ALUMINIUM; FATIGUE; RESEARCH REACTORS; PRESSURE VESSELS; WELDED JOINTS; NEUTRON SOURCES |
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| Availability: | OSTI; NTIS; GPO Dep.; |
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| Update Date: | 2009 Dec 14 |
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