A methodology for on-line fatigue life monitoring of Indian nuclear power plant components
Creators
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
Description
Fatigue is one of the most important aging effects of nuclear power plant components. Information about accumulation of fatigue helps in assessing structural degradation of the components. This assists in-service inspection and maintenance and may also support future life extension program of a plant. In the present report a methodology is being proposed for monitoring on line fatigue life of nuclear power plant components using available plant instrumentations. Major factors affecting fatigue life of a nuclear power plant components are the fluctuations of temperature, pressure and flow rate. Green's function technique is used in on line fatigue monitoring as computation time is much less than finite element method. A code has been developed which computes temperature and stress Green's functions in 2-D and axisymmetric structure by finite element method due to unit change in various fluid parameters. A post processor has also been developed which computes the temperature and stress responses using corresponding Green's functions and actual fluctuation in fluid parameters. In this post processor, the multiple site problem is solved by superimposing single site Green's function technique. It is also shown that Green's function technique is best suited for on line fatigue life monitoring of nuclear power plant components. (author). 6 refs., 43 figs
Availability note (English)
MF available from INIS under the Report Number.Files
24038602.pdf
Files
(511.8 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- BARC--1992/E/019
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 24038602
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AGING; CYLINDERS; FATIGUE; FINITE ELEMENT METHOD; G CODES; GREEN FUNCTION; MONITORING; NOZZLES; NUCLEAR POWER PLANTS; ON-LINE SYSTEMS; PIPES; REACTOR COMPONENTS; STRESSES; TEMPERATURE NOISE; TRANSIENTS; VARIATIONS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; FUNCTIONS; MECHANICAL PROPERTIES; NOISE; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; THERMAL POWER PLANTS