Reliability analysis of stiff versus flexible piping. Status report
Conservative design procedures adopted for nuclear piping systems usually result in stiff piping designs that use excessive support devices such as rigid supports and snubbers. Use of these piping support devices has created safety concerns. This report describes the interim result for a piping research project conducted at Lawrence Livermore National Laboratory (LLNL) for the US Nuclear Regulatory Commission (NRC). The overall objective of this research project is to develop modified design requirements and criteria which will improve piping reliability and minimize the use of pipe supports, snubbers, and pipe whip restraints. The current study was conducted to establish the necessary groundwork for this work based on the piping reliability analysis.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6978538
- Report Number(s):
- NUREG/CR-3718; UCID-19722; ON: DE84010562
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
MECHANICAL STRUCTURES
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
RESTRAINTS
SEISMIC EFFECTS
SHOCK ABSORBERS
STRESS ANALYSIS
STRESSES
SUPPORTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
MECHANICAL STRUCTURES
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
RESTRAINTS
SEISMIC EFFECTS
SHOCK ABSORBERS
STRESS ANALYSIS
STRESSES
SUPPORTS
WATER COOLED REACTORS
WATER MODERATED REACTORS