Published June 2014
| Version v1
Journal article
Study on fatigue of reactor coolant piping and minimum piping wall thickness
Creators
- 1. Nuclear Equipment Reliability and Safety Center, China Academy of Machinery, Beijing (China)
Description
As a core issue in fatigue qualification for nuclear power plant reactor coolant piping, FEM thermal transient analysis are used to pursue the wall thickness thermal field, instead of finite difference equation, which could be brought to the Code equation for fatigue analysis by solving the transient alternating stress amplitude. Calculation methodology, Optimization algorithm for minimum wall thickness, and flow chart of iterative solution are addressed in this paper, those items can be achieved programmatically. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 35
- Journal Issue
- 3
- Journal Page Range
- p. 46-50
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48083559
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; AMPLITUDES; DIAGRAMS; EQUATIONS; FATIGUE; ITERATIVE METHODS; NUCLEAR POWER PLANTS; OPTIMIZATION; PIPELINES; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STRESSES; THICKNESS; TRANSIENTS; WALLS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; DIMENSIONS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL LOGIC; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs., 1 tab., 5 refs.