Reliability analysis of stiff versus flexible piping. Status report
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 - GPO $3.75 as DE84010562.
Files
Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- NUREG/CR--3718
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15072936
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RELIABILITY; RESTRAINTS; SEISMIC EFFECTS; SHOCK ABSORBERS; STRESS ANALYSIS; STRESSES; SUPPORTS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICAL STRUCTURES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- UCID--19722.