Fatigue evaluation of ASME Class 1 components considering the environmental effects

Conference · Fri Dec 01 00:00:00 EST 1995

OSTI ID:136834

Neto, M M ^[1]; Maneschy, E ^[2]

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1. Brazilian Commission for the Nuclear Energy, Sao Paulo (Brazil)
2. FURNAS/COPESP, Sao Paulo (Brazil)

A discussion considering fatigue design basis (FDB) and fatigue operating basis (FOB) approaches is presented. These two concepts are applied to evaluate the lifetime of typical ASME 3 class 1 components through simplified and detailed stress analysis. The cumulative usage factor (CUF) calculated using S-N fatigue curves available in the ASME 3 are compared to those obtained by S-N curves modified by the reactor environment. Some recommendations are presented to assess the fatigue in nuclear power plants structures.

• OSTI ID: 136834
• Report Number(s): CONF-950740-; ISBN 0-7918-1344-4; TRN: 96:000950
• Resource Relation: Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of International pressure vessels and piping codes and standards. Volume 2: Current perspectives; PVP-Volume 313-2; Rao, K.R.; Asada, Yasuhide; Adams, T.M. [eds.] [and others]; PB: 505 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
NUCLEAR POWER PLANTS
REACTOR COMPONENTS
EQUIPMENT
FATIGUE
SERVICE LIFE
AUXILIARY SYSTEMS
FEEDWATER
PRESSURIZERS
TEMPERATURE DEPENDENCE
WATER CHEMISTRY