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Reconstruction of metal embrittlement in a reactor vessel of the atomic icebreaker Lenin

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Atomic Energy Aims and scope

Data from a study of radiation damage to the vessel of a reactor from the retired atomic icebreaker Lenin are used to determine the radiation embrittlement characteristics of the metal. Irradiation by a low neutron flux of 1010–1011 cm−2sec−1 at the beginning of operation is found to correspond to more intense embrittlement of the metal. Then, apparently, as harmful elements are depleted in the matrix of the metal, embrittlement is reduced until there is a change in sign relative to the standard curve obtained for neutron fluxes above 1013 cm−2sec−1. It is proposed that, because of irradiation by low fluxes of neutrons in the peripheral zones of reactor vessels during some stages of operation, these zones may be damaged to a greater extent than those lying closer to the core. The irradiating neutron flux is a factor that influences the embrittlement of reactor vessel materials, so there is some interest in studying how material is damaged in the vessels of power reactors with low radiation loads which are under development. This is also needed in order to evaluate the efficacy of measures undertaken to reduce the effect of neutron irradiation on reactor vessels.

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References

  1. A. Fabry, J. Velde, J. Puzzolante, et al., “Research to understand the embrittlement behavior of Yankee/BR3 surveillance plate and other outlier RPV steels,” in: Am. Soc. for Testing and Materials Special Technical Publication, 1270 (1996), pp. 138–139.

    Google Scholar 

  2. R. Gerard, A. Fabry, J. Velde, et al., “In-service embrittlement of the pressure vessel welds at the Doel I and Doel II nuclear power plants,” ibid., pp. 294–319.

    Google Scholar 

  3. T. Marston and K. Stahlkopf, “Radiation embrittlement and significance of its effects on integrity and operation of LWR pressure vessels,” Nucl. Safety, 21, No. 6, 724–730 (1980).

    Google Scholar 

  4. J. Knott and C. English, “Views of TAGSI on the principles underlying the assessment of the mechanical properties of irradiated ferritic steel reactor pressure vessels,” Int. J. Pressure Vessels and Piping, 76, 891–901 (1999).

    Article  Google Scholar 

  5. E. A. Kuleshova, B. A. Gurovich, Y. I. Shtrombakh, et al., “Microstructural behavior of VVER-440 reactor pressure vessel steels under irradiation,” J. Nucl. Mater., 342, 77–89 (2005).

    Article  ADS  Google Scholar 

  6. K. Kussmaul, J. Fohl, and T. Weissenberg, “Assurance of the pressure vessel integrity with respect to irradiation embrittlement: activities in the FRG,” in: Am. Soc. for Testing and Materials Special Technical Publication, 1011 (1989), pp. 3–26.

    Google Scholar 

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Translated from Atomnaya Énergiya, Vol. 105, No. 4, pp. 201–205, October, 2008.

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Krasikov, E.A., Nikolaenko, V.A. Reconstruction of metal embrittlement in a reactor vessel of the atomic icebreaker Lenin. At Energy 105, 257–261 (2008). https://doi.org/10.1007/s10512-009-9094-5

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  • DOI: https://doi.org/10.1007/s10512-009-9094-5

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