Published 1992
| Version v1
Book
A sample fatigue problem solved with finite elements and transfer function method
Description
Determining the usage factor of a component of the primary circuit of a Nuclear Power Plant comes after lengthy calculations, generally performed with the Finite Element Method. Each thermal transient, defined in operating specifications, is analyzed or covered by an umbrella transient. This methodology has been superseded by Framatome Calculation Department (St Marcel Plant) by the Transfer Function method implemented in the Finite Element program SYSNUKE
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0774-6
- Imprint Title
- Pressure vessel fracture, fatigue, and life management: PVP-Volume 233
- Imprint Pagination
- 312 p.
- Journal Page Range
- p. 147-151.
Conference
- Title
- American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 21-25 Jun 1992.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058443
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; FATIGUE; NUCLEAR POWER PLANTS; PERFORMANCE; PRIMARY COOLANT CIRCUITS; S CODES; THERMAL SHOCK
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-920631--.