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., 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
- 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:5549197
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:6671261
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:6653880
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
COMPONENTS AND ACCESSORIES
CREEP
DEFORMATION
FATIGUE
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
NUCLEAR POWER PLANTS
PIPES
REACTOR COMPONENTS
SPECIFICATIONS
STAINLESS STEEL-316
STANDARDS
STANDARDS DOCUMENT
STRESS ANALYSIS
STRESSES
TEMPERATURE EFFECTS
TEMPERATURE RANGE 0400-1000 K
WELDED JOINTS
220200
COMPONENTS AND ACCESSORIES
CREEP
DEFORMATION
FATIGUE
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
NUCLEAR POWER PLANTS
PIPES
REACTOR COMPONENTS
SPECIFICATIONS
STAINLESS STEEL-316
STANDARDS
STANDARDS DOCUMENT
STRESS ANALYSIS
STRESSES
TEMPERATURE EFFECTS
TEMPERATURE RANGE 0400-1000 K
WELDED JOINTS