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Title: Materials and design bases issues in ASME Code Case N-47

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.
Authors:
;
Publication Date:
OSTI Identifier:
6357626
Report Number(s):
NUREG/CR-5955; ORNL/TM--12266
ON: TI93012887
DOE Contract Number:
AC05-84OR21400
Resource Type:
Technical Report
Research Org:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab., TN (United States)
Sponsoring Org:
NRC; Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:
United States
Language:
English
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 210700* -- Nuclear Power Plants-- Regulation & Licensing; 220200 -- Nuclear Reactor Technology-- Components & Accessories