Materials and design bases issues in ASME Code Case N-47
- Oak Ridge National Lab., TN (United States)
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.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6357626
- Report Number(s):
- NUREG/CR-5955; ORNL/TM-12266; ON: TI93012887
- Country of Publication:
- United States
- Language:
- English
Similar Records
Materials and design bases issues in ASME Code Case N-47
Code qualification of structural materials for AFCI advanced recycling reactors.
Advancements Toward ASME Nuclear Code Case for Compact Heat Exchangers
Technical Report
·
Thu Apr 01 00:00:00 EST 1993
·
OSTI ID:6357626
Code qualification of structural materials for AFCI advanced recycling reactors.
Technical Report
·
Thu May 31 00:00:00 EDT 2012
·
OSTI ID:6357626
+2 more
Advancements Toward ASME Nuclear Code Case for Compact Heat Exchangers
Technical Report
·
Wed Sep 22 00:00:00 EDT 2021
·
OSTI ID:6357626
Related Subjects
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
210700* - Nuclear Power Plants- Regulation & Licensing
220200 - Nuclear Reactor Technology- Components & Accessories
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
210700* - Nuclear Power Plants- Regulation & Licensing
220200 - Nuclear Reactor Technology- Components & Accessories