Technical considerations for flexible piping design in nuclear power plants
Description
The overall objective of this research project is to develop a technical basis for flexible piping designs which will improve piping reliability and minimize the use of pipe supports, snubbers, and whip restraints. The current study was conducted to establish the necessary groundwork based on the piping reliability analysis. A confirmatory piping reliability assessment indicated that removing rigid supports and snubbers tends, to either improve or affect very little the piping reliability. We then investigated a couple of changes to be implemented in Regulatory Guide (RG) 1.61 and RG 1.122 aimed at more flexible piping design. We concluded that these changes substantially reduce calculated piping responses and allow piping redesigns with significant reduction in number of supports and snubbers without violating ASME code requirements. Furthermore, the more flexible piping redesigns are capable of exhibiting reliability levels equal to or higher than the original stiffer design. An investigation of the malfunction of pipe whip restraints confirmed that the malfunction introduced higher thermal stresses and tended to reduce the overall piping reliability. Finally, support and component reliabilities were evaluated based on available fragility data. The results indicate that the support reliability usually exhibits a moderate decrease as the piping flexibility increases. Most on-line pumps and valves showed an insignificant reduction in reliability for a more flexible piping design
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Proceedings of the 1985 pressure vessels and piping conference. Volume PVP-98-3. Recent advances in seismic design of piping and components
- Journal Page Range
- p. 133-138.
Conference
- Title
- ASME Pressure Vessel and Piping Division conference.
- Dates
- 24-29 Jun 1985.
- Place
- New Orleans, LA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17073367
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLEXIBILITY; NUCLEAR POWER PLANTS; PIPES; PUMPS; REACTOR COOLING SYSTEMS; RELIABILITY; RESEARCH PROGRAMS; SEISMIC EFFECTS; SPECIFICATIONS; SUPPORTS; THERMAL STRESSES; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; EQUIPMENT; FLOW REGULATORS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; STRESSES; TENSILE PROPERTIES; THERMAL POWER PLANTS