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A preliminary evaluation of the design bases (principally ASME Code Case N-47) was conducted for design and operation of reactors at elevated temperatures where the time-dependent effects of creep, creep-fatigue, and creep ratcheting are significant. Areas where Code rules or regulatory guides may be lacking or inadequate to ensure the operation over the expected life cycles for the next-generation advanced high-temperature reactor systems, with designs to be certified by the US Nuclear Regulatory Commission, have been identified as unresolved issues. Twenty-two unresolved issues were identified and brief scoping plans developed for resolving these issues.
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| Authors: |
Huddleston, R.L.;
Swindeman, R.W. (Oak Ridge National Lab., TN (United States))
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| Publication Date: | 1993 Apr 01 |
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| OSTI Identifier: | OSTI ID: 6357626; Legacy ID: TI93012887 |
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| Report Number(s): | NUREG/CR-5955; ORNL/TM--12266 |
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| DOE Contract Number: | AC05-84OR21400 |
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| Resource Type: | Technical Report |
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| Research Org: | Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab., TN (United States) |
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| Sponsoring Org: | NRC; Nuclear Regulatory Commission, 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: Pages: (34 p) |
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| Other Number(s): | Other: ON: TI93012887 |
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| Subject: | 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR MATERIALS; TEMPERATURE DEPENDENCE; REACTORS; DESIGN; OPERATION; CORROSION; CREEP; FATIGUE; REGULATIONS; STANDARDS; TEMPERATURE RANGE 0400-1000 K; CHEMICAL REACTIONS; MATERIALS; MECHANICAL PROPERTIES; TEMPERATURE RANGE |
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| Availability: | OSTI; NTIS; INIS; GPO |
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| Update Date: | 2008 Feb 07 |
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