Inservice Data Reporting and Analysis for Pressure Vessels, Piping, Pumps, and Valves: Presented at the Winter Annual Meeting of the American Society of Mechanical Engineers, San Francisco, California, December 10-15, 1978, Volume 1Jeffrey Tse-wei Fong |
Contents
The Nuclear Plant Reliability Data System | 1 |
Survey of Defects in Pressure Vessels Built to High Standards of Construction | 21 |
Data Collection in a Nuclear Power Plant and a Pilot Collection System in a Lignite | 55 |
Copyright | |
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Common terms and phrases
ASME boiler breakdown Category Cause of Failure Code construction Corrosion fatigue cost data base data collection data processing defects Delphi electric power industry equipment estimate evaluation factors failure analysis failure cause Failure due failure modes failure rate Figure fillet weld fracture header includes Indication and Consequences industry input Item and Dimensions lb/in² leakage leaks maintenance manufacturers mechanical method Mild steel Press MTBR MTTF nozzle NPRDS nuclear power plants Nuclear Regulatory Commission number of failures operating Outage output parameters piping systems population at risk Pressure Vessel problem Reactor repair requirements safety Saint-Laurent-des-Eaux seal purge system shell Snubbers Southwest Research Institute Standards statistical Steam generating unit Steam receiver stress Superheated steam Superheater systems and components Table temperature Thermal thick total number tube utility valves Water hammer water pumps weld weld Cracking λε