Acta Mechanica Slovaca 2021, 25(1):60-66 | DOI: 10.21496/ams.2021.016

Advanced uses of Stress Intensity Factor Tables in PTS Calculations of Nuclear Power Plants

Tamás Pálfi1, *
1 VEIKI Energia+ Ltd, 47 Murányi utca, Budapest, 1078 Hungary

This paper introduces an approximation method developed for calculating stress intensity factor for pressure vessels in nuclear power plants. The method is based on weight functions, which has high accuracy among the methods based on crack-free stress calculations. Besides it has the advantage over the weight functions method, it corresponds to the approximation methods can be found in nuclear codes like ASME BPVC [1]. Numerical test calculations are performed to experimentally show the differences of several possible approximation methods. The results show the weighted least squares method using stress intensity factor weight functions, do have the above-mentioned advantages.

Keywords: fracture mechanics; stress intensity factors; weight functions; nuclear power plants;

Received: March 8, 2021; Revised: March 9, 2021; Accepted: March 17, 2021; Published: March 26, 2021  Show citation

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Pálfi, T. (2021). Advanced uses of Stress Intensity Factor Tables in PTS Calculations of Nuclear Power Plants. Acta Mechanica Slovaca, 25(1), 60-66. doi: 10.21496/ams.2021.016
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    References

    1. ASME Boiler & Pressure Vessel Code (2007). Division 1 Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. ASME, The American Society of Mechanical Engineers. New York.
    2. Anderson, T. L. (2011). Fracture Mechanics - Fundamentals and Applications. CRC Press Taylor & Francis, Boca Raton.
    3. Schmitt W., Keim E. (1979). Linear Elastic Analysis of Semi-Elliptical Axial Surface Cracks in a Hollow Cylinder. International Journal of Pressure Vessels and Piping, Volume 7, Issue 2, pp 105-118. Go to original source...
    4. Pálfi T., Osztheimer M, Janosiné Bíró Á. (2011) PTS vizsgálatok részletes ellenőrző számításainak elvégzése. Scientific report for the Hungarian Atomic Energy Authority. VEIKI E+ Ltd.., Budapest, Hungary.
    5. Marie, S.; Menager, Y.; Chapuliot, S. (2005). Stress Intensity Factors for Underclad and Through Clad Defects in a Reactor Pressure Vessel Submitted to a Pressurised Thermal Shock. International Journal of Pressure Vessels and Piping, Volume 82, Issue 10, pp 746-760. Go to original source...

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