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Article

  • Title

    POSSIBILITY OF A LIFE-TIME EXTENSION FOR WWER-1000 REACTOR PRESSURE VESSELS BEYOND THE DESIGN PERIOD

  • Authors

    Holiak M.
    Revka V.
    Chyrko L.
    Trygubenko O.
    Chaikovsky Yu.

  • Subject

    ENERGETICS. HEAT ENGINEERING. ELECTRICAL ENGINEERING

  • Year 2020
    Issue 1(60)
    UDC 621.039.577:620.193.2
    DOI 10.15276/opu.1.60.2020.11
    Pages 103-108
  • Abstract

    At present a life-time extension for WWER-1000 reactor pressure vessels is an actual issue in Ukraine. For a decision about the life-time extension it is needed to assess mechanical properties and the critical brittleness temperature TK for the RPV materials as well as to perform the brittle strength calculations. The surveillance test data for the reactor pressure vessel in ques- tion are used for an estimation of changes in the mechanical properties. For today dose dependences of the temperature TK for weld metal in the fluence range of fast (E ≥ 0.5 MeV) neutrons, corresponding to the RPV lifetime more than 40 years, have been obtained. This paper analyzes the surveillance test data for the WWER-1000 reactor pressure vessels, whose welds have a high content of nickel and manganese and are prone to considerable radiation embrittlement. The surveillance specimens have been irradiated within the fluence range, the maximum value of which exceeds the design fluence 57·1022 m–2. The analysis has shown that the experimental dependences of the temperature TK on the neutron fluence for welds are consistent with the design embrittlement model with the exponent of 1/3. The results of comparison between the critical brittleness temperature and the maximum allowable value TKa indicate a possibility of the life-time extension for WWER-1000 reactor pressure vessels beyond the design period.

  • Keywords fast neutrons fluence, surveillance specimens, long-term operation, reactor pressure vessel
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  • References

    Література

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    References

    1. Malerba, L., Nordlund, K., & Sand, A.E. et al. (2018). Primary radiation damage: A review of current understanding and models. Journal of Nuclear Materials, 512, 450–479.

    2. Malerba, L., Bonny, G., & Terentyev, D. et al. (2013). On the thermal stability of late blooming phases in reactor pressure vessel steels: An atomistic study. Journal of Nuclear Materials, 442(1–3), 282–291.

    3. PNAE G-7-002-86. Standards for calculating the strength of equipment and pipelines of nuclear power plants. (1989). Moscow: Energoatomizdat, 525 p.

    4. SOU NAYK 087: 2015 Methodology for the determination of radiation embrittlement of metal in reac- tor vessels according to the test results of witness samples. (2018). 29 p.

    5. Eason, E.D., Odette, G.R., Nanstad, R.K., & Yamamoto, T. (2013). A physically-based correlation tran- sition temperature shifts for RPV steels. Jornal of Nuclear Materials, 423, 240–254.

    6. Odette G.R., Yamamoto T., Nanstad R.K. et al. (2017). Embrittlement of Reactor Pressure Vessel Steels under Extended Service Conditions: The Status and Implications of the UCSB ATR-2 Experiment. 4th International Conference on Nuclear Power Plant Life Management Session 3-4 (presentation IAEA- CN-246-055). October 23rd – 27th, 2017 Lyon, France. P. 20.

    7. Odette, G.R. & Nanstad, R.K. (2009). Predictive Reactor Pressure Vessel Steel Irradiation Embrittlement Models: Issues and Opportunities. JOM, Materials Issues in Nuclear Reactor Overview. 61, 7, 17–23.

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