Requirements for design of Class 1 elevated temperature nuclear system components (supplement to ASME Code Case N-47)
This standard provides rules for the design of Class 1 nuclear components for use at elevated temperatures. It constitutes a complete set of requirements only when used in conjunction with Section III of the ASME Boiler and Pressure Vessel Code (ASME Code) and addenda, and ASME Code Case N-47. Unmodified portions of Code Case N-47 are not repeated in this standard but are considered requirements of this standard.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10137673
- Report Number(s):
- NE-F-9-4T-Rev.2/84; ON: DE93011216
- Resource Relation:
- Other Information: PBD: Jun 1986
- Country of Publication:
- United States
- Language:
- English
Similar Records
Requirements for design of Class 1 elevated temperature nuclear system components (supplement to ASME Code Case N-47)
Requirements for design of Class 1 elevated temperature nuclear system components (supplement to ASME Code Case N-47)
Requirements for construction of Class 1 elevated temperature nuclear system components (supplement to ASME code cases N-47, N-48, N-49, N-50, and N-51)
Technical Report
·
Mon Jun 30 00:00:00 EDT 1986
·
OSTI ID:10137673
Requirements for design of Class 1 elevated temperature nuclear system components (supplement to ASME Code Case N-47)
Technical Report
·
Sun Jun 01 00:00:00 EDT 1986
·
OSTI ID:10137673
Requirements for construction of Class 1 elevated temperature nuclear system components (supplement to ASME code cases N-47, N-48, N-49, N-50, and N-51)
Technical Report
·
Wed Sep 01 00:00:00 EDT 1982
·
OSTI ID:10137673
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
REACTOR COMPONENTS
SPECIFICATIONS
STANDARDS
STANDARDS DOCUMENT
STRESSES
MECHANICAL PROPERTIES
STRESS ANALYSIS
FRACTURE PROPERTIES
FATIGUE
CREEP
DEFORMATION
WELDED JOINTS
PIPES
STAINLESS STEEL-316
TEMPERATURE RANGE 0400-1000 K
TEMPERATURE EFFECTS
220200
COMPONENTS AND ACCESSORIES
NUCLEAR POWER PLANTS
REACTOR COMPONENTS
SPECIFICATIONS
STANDARDS
STANDARDS DOCUMENT
STRESSES
MECHANICAL PROPERTIES
STRESS ANALYSIS
FRACTURE PROPERTIES
FATIGUE
CREEP
DEFORMATION
WELDED JOINTS
PIPES
STAINLESS STEEL-316
TEMPERATURE RANGE 0400-1000 K
TEMPERATURE EFFECTS
220200
COMPONENTS AND ACCESSORIES