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Two-Dimensional Numerical Analysis of Irradiation Swelling in WWER-1000 Reactor Baffle with Variation of Input Data on Volumetric Heat Generation and Damaging Dose

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The paper addresses the currently available mathematical models of irradiation swelling of austenitic steel 08Kh18N10T which is used for the manufacture of WWER-1000 reactor internals: the models of free swelling, which take into account temperature and damaging dose, and the model that includes a stress state. The irradiation creep phenomenon is taken into consideration too. The authors review the input data such as the volumetric heat generation, temperature, and damaging dose in a baffle and core barrel of WWER-1000 reactor; based on these data a two-dimension computational assessment of irradiation swelling of reactor internals has been performed and is followed by a comparative analysis of the results. The latter shows how the input data variation affects the calculated results. Evaluation of the baffle form change suggests that the baffle may have a contact interaction with the core barrel.

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References

  1. S. N. Votinov, V. I. Prokhorov, and Z. E. Ostrovskii, Irradiated Stainless Steels [in Russian], Nauka, Moscow (1987).

    Google Scholar 

  2. I. P. Kursevich, B. Z. Margolin, O. Yu. Prokoshev, et al., “Mechanical properties of austenitic steels under neutron irradiation. The influence of various factors,” Vopr. Materialoved., No. 4 (48), 55–68 (2006).

  3. N. K. Vasina, B. Z. Margolin, A. G. Gulenko, et al., “Irradiation swelling of austenitic stainless steels. The Influence of various factors. Processing of experimental data and formulation of constitutive equations,” Vopr. Materialoved., No. 4 (48), 69–89 (2006).

  4. A. A. Sorokin, B. Z. Margolin, and I. P. Kursevich, et al., “The influence of neutron irradiation on mechanical properties of materials of WWER type reactor internals,” Vopr. Materialoved., No. 2 (66), 131–151 (2011).

  5. B. Z. Margolin, A. I. Murashova, and V. S. Neustroev, “Analysis of the influence of type of stress state on radiation swelling and radiation creep of austenitic steels,” Strength Mater., 44, No. 3, 227–240 (2012).

    Article  Google Scholar 

  6. O. V. Borodin, V. V. Bryk, V. N. Voevodin, et al., “Microstructural mechanisms of low-temperature irradiation swelling and embrittlement of materials of WWER-1000 reactor internals,” in: B. E. Paton (Ed.), Problems of Service Life and Operational Safety of Structures, Facilities, and Machinery [in Ukrainian], Paton Electric Welding Institute, National Academy of Sciences of Ukraine, Kyiv (2006), pp. 161–166.

    Google Scholar 

  7. A. S. Kal’chenko, V. V. Bryk, V. N. Voevodin, and N. P. Lazarev, “Modeling of swelling in Kh18N10T steel under simulating and reactor operating conditions,” Vopr. Atom. Nauki Tekhn., No. 4-2, 131–139 (2009).

  8. A. S. Kalchenko, V. V. Bryk, N. P. Lazarev, et al., “Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates,” J. Nucl. Mater., 399, 114–121 (2010).

    Article  Google Scholar 

  9. A. S. Kal’chenko, V. V. Bryk, V. N. Voevodin, et al., “Prediction of irradiation swelling of WWER-1000 reactor baffle for an operation period of 30 to 60 years,” Yader. Fiz. Énerg., 12, No. 1, 69–78 (2011).

    Google Scholar 

  10. A. S. Kal’chenko, V. V. Bryk, V. N. Voevodin, et al., “Elaboration of a procedure for substantiating the possibility of extending safe operating life of WWER-1000 reactor internals,” in: B. E. Paton (Ed.), Problems of Service Life and Operational Safety of Structures, Facilities, and Machinery [in Ukrainian], Paton Electric Welding Institute, National Academy of Sciences of Ukraine, Kyiv (2012), pp. 149–153.

    Google Scholar 

  11. A. S. Kalchenko, V. V. Bryk, N. P. Lazarev, et al., “Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30-60 years,” J. Nucl. Mater., 437, 415–423 (2013).

    Article  Google Scholar 

  12. V. M. Troyanov, Yu. I. Likhachev, M. Ya. Khmelevskii, et al., “Assessment and analysis of thermomechanical behavior of elements of WWER reactor internals allowing for the irradiation effects,” in: Collected Papers of the Vth Inter-Branch Conference on Reactor Material Science (Dimitrovgrad, September 8–12, 1997) [in Russia], Volume 2, Part 1, Dimitrovgrad (1998), pp. 3–18.

  13. B. Margolin, I. Kursevitch, and V. Fedorova, “Influence of neutron irradiation and environment on materials properties of internals of VVER reactors,” in: Technical Meeting on Irradiation Embrittlement and Life Time Management of Reactor Pressure Vessels in Nuclear Power Plants (Oct. 18–22, 2010, Znojmo), Czech Republic (2010).

  14. B. Margolin, V. Fedorova, A. Sorokin, et al., “The mechanisms of material degradation under neutron irradiation for WWER internals and methods for structural integrity assessment,” in: Proc. of Int. Conf. “Structural Integrity and Life of NPP Equipment” (Oct. 2–5, 2012, Kiev), Kiev (2012).

  15. A. A. Afanas’ev, “Improving cost effectiveness of fuel cycles of WWER-1000 reactor by increasing fuel burn-up,” Vopr. Atom. Nauki Tekhn., No. 6 (45), 45–56 (2000).

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Correspondence to O. V. Makhnenko.

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Translated from Problemy Prochnosti, No. 5, pp. 127 – 139, September – October, 2014.

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Makhnenko, O.V., Mirzov, I.V. Two-Dimensional Numerical Analysis of Irradiation Swelling in WWER-1000 Reactor Baffle with Variation of Input Data on Volumetric Heat Generation and Damaging Dose. Strength Mater 46, 689–699 (2014). https://doi.org/10.1007/s11223-014-9603-1

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  • DOI: https://doi.org/10.1007/s11223-014-9603-1

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