Guidelines and procedures for design of Class 1 elevated temperature nuclear system components

Technical Report · Mon Sep 01 00:00:00 EDT 1986

DOI:https://doi.org/10.2172/6682954· OSTI ID:6682954

This standard provides guidelines and procedures which may be used by the manufacturer in satisfying the requirements given for design of class 1 elevated temperature nuclear system components. Guidance is given regarding planning and control of design analysis. A sequence for calculations is recommended. Methods of analysis, including procedures to account for environmental effects, are given which are acceptable in principle to the owner. A format is provided for use in documentation of design analyses.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6682954
• Report Number(s): NE-F-9-5T-Rev.10/86; ON: DE93011215
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
REACTOR COMPONENTS
SPECIFICATIONS
STANDARDS
REACTOR MATERIALS
TEMPERATURE EFFECTS
COMPUTER CODES
CREEP
DEFORMATION
DESIGN
ELASTICITY
FATIGUE
MECHANICAL PROPERTIES
PLASTICITY
STAINLESS STEEL-304
STAINLESS STEEL-316
STANDARDS DOCUMENT
STRAINS
STRESSES
TEMPERATURE RANGE 0400-1000 K
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEAR FACILITIES
POWER PLANTS
STAINLESS STEELS
STEEL-CR17NI12MO3
STEEL-CR19NI10
STEELS
TEMPERATURE RANGE
TENSILE PROPERTIES
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220200* - Nuclear Reactor Technology- Components & Accessories