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
NPRDS 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 component failures construction Corrosion fatigue cost data base data processing defects Delphi electric power industry engineering data equipment estimate evaluation examination factors failure analysis Failure Cause Failure due failure modes failure rate Figure fillet weld fracture header includes input Item and Dimensions lb/in² leakage leaks listed maintenance manufacturers mechanical method Mild steel Press 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 replacement requirements safety Saint-Laurent-des-Eaux seal purge system shell Snubbers Specification Service Temp Standards statistical Steam Cracking Steam generating unit Steam receiver steel Press Temp stress Superheated steam Superheater systems and components Table temperature Thermal tube utility valves Water hammer water pumps weld weld Cracking λε