Published April 1993
| Version v1
Report
Restricted
Materials and design bases issues in ASME Code Case N-47
Creators
- 1. Oak Ridge National Lab., TN (United States)
Description
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
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI93012887; NTIS; INIS; GPO.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- NUREG/CR--5955
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24073085
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CORROSION; CREEP; DESIGN; FATIGUE; OPERATION; REACTOR MATERIALS; REACTORS; REGULATIONS; STANDARDS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- CHEMICAL REACTIONS; LAWS; MATERIALS; MECHANICAL PROPERTIES; TEMPERATURE RANGE
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ORNL/TM--12266.