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Some Aspects of Inclusion of Loading History in the Fracture Strength Analysis of Reactor Pressure Vessels Under Thermal Shock Conditions

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The paper addresses some aspects of inclusion of loading history in the fracture strength analysis of reactor pressure vessels under thermal shock conditions. The strength assessment of a reactor pressure vessel and its lifetime extension are shown to essentially depend on reliability of results of elastic-plastic modeling of stress-strain kinetics and determination of design values of the fracture mechanics parameters. The present findings of the finite-element analysis demonstrate that the loading history must be taken into account in the determination of the temperature dependence of stress intensity factor for a postulated specified crack. It is shown that, in the fracture toughness analysis of a reactor pressure vessel, the temperature dependence of the stress intensity factor has to be derived from the results of the analysis of kinetics and mode of loading of metal at the crack tip under thermal shock conditions. For construction of the above dependence, we proposed approach, which accounts for the active loading and unloading processes occurring in the metal in the crack front vicinity. Incorporation of the loading history into the analysis of the temperature dependence of the stress intensity factor using the proposed approach forcan permit revealing some additional margin of strength during the substantiation of lifetime extension for a reactor pressure vessel under thermal shock conditions.

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References

  1. Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs (VERLIFE), Version 2008.

  2. Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment, IAEA-TECDOC-1627, Vienna (2010).

  3. RD ÉO 0606-2005. Calculation Procedure for Brittle Fracture Resistance Analysis of NPP WWER Reactor Pressure Vessels (MRKR-SKhR-2004) [in Russian], St. Petersburg–Moscow (2004).

  4. V. V. Kharchenko, G. V. Stepanov, et al., MT-D.0.03.391-06. Procedure of Strength and Lifetime Assessment for WWER Reactor Pressure Vessels in Operation [in Russian], Kiev (2009).

  5. V. V. Kharchenko, V. A. Piminov, A. Yu. Chirkov, et al., “Elastoplastic fracture resistance analysis of NPP primary circuit equipment elements,” Strength Mater., 45, No. 4, 397–405 (2013).

    Article  Google Scholar 

  6. V. V. Kharchenko, A. Yu. Chirkov, S. V. Kobel’skii, et al., “The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock,” Strength Mater., 42, No. 1, 17–24 (2010).

    Article  Google Scholar 

  7. V. V. Kharchenko, O. Yu. Chirkov, S. V. Kobel’skyi, et al., “Further development of the methodology of fracture strength calculation of NPP equipment elements,” in: Strength of Materials and Theory of Structures [in Ukrainian], Collected Papers, Issue 94, KNUBA, Kyiv (2015), pp. 59–74.

  8. G. P. Cherepanov, Brittle Fracture Mechanics [in Russian], Nauka, Moscow (1974).

    Google Scholar 

  9. H. G. deLorenzi, “On the energy release rate and the J-integral for 3-D crack configurations,” Int. J. Fracture, 19, No. 3, 183–193 (1982).

  10. G. P. Nikishkov, “Computation of energy integral by the equivalent volume integration method,” in: S. N. Atluri (Ed.), Computational Methods in the Mechanics of Fracture [Russian translation], Mir, Moscow (1990), pp. 365–367.

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Translated from Problemy Prochnosti, No. 5, pp. 14 – 21, September – October, 2016.

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Kharchenko, V.V., Chirkov, A.Y. Some Aspects of Inclusion of Loading History in the Fracture Strength Analysis of Reactor Pressure Vessels Under Thermal Shock Conditions. Strength Mater 48, 603–609 (2016). https://doi.org/10.1007/s11223-016-9803-y

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  • DOI: https://doi.org/10.1007/s11223-016-9803-y

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