Preliminary analysis and screening criteria for elevated temperature piping

Conference · Mon Jan 01 00:00:00 EST 1979

OSTI ID:5688400

Minami, H M; Naugle, F V

The complexities of the ASME Class 1 nuclear elevated temperature structural design criteria precludes the possibility of performing a complete Code Case 1592 analysis for all of the alternative designs normally investigated in the course of the design of a Liquid Metal Fast Breeder Reactor (LMFBR) high-temperature piping system. To enable the piping design to proceed on an orderly controlled basis, the piping design analysis is separated into the following phases: (a) screening analysis to determine pipe routing feasibility, (b) preliminary analysis to determine pipe support configuration, and (c) final design analysis (including transients) to demonstrate Code compliance. The application of the first phases of this procedure is demonstrated by a summary of the analyses performed in the development of the preliminary design configuration for the primary system of a commercialized LMFBR.

• DOE Contract Number: EY-76-C-03-0824-021
• OSTI ID: 5688400
• Report Number(s): CONF-790615-28; TRN: 80-000867
• Resource Relation: Conference: 3. US national congress on pressure vessels and piping, San Francisco, CA, USA, 25 Jun 1979; Related Information: ASME Publication 79-NE-6
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
PIPES
STRESS ANALYSIS
FATIGUE
STRESSES
BREEDER REACTORS
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MECHANICAL PROPERTIES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
210500* - Power Reactors
Breeding