Methods to obtain of representative results of surveillance-specimens investigation for assessment of radiation embrittlement of reactor vessel materials WWER-1000 type reactor

Authors

  • Виталий Георгиевич Ковыршин NPP Operation Support Institute N.Vasilenko Street, 7, Kyiv, Ukraine, 03124, Ukraine https://orcid.org/0000-0001-7709-8112
  • Александр Владимирович Сахно State scientific and technical center for nuclear and radiation safety V.Stusa Street, 35/37, Kyiv, Ukraine, 03142, Ukraine https://orcid.org/0000-0002-3411-3308
  • Валентина Александровна Григорьева National Technical University of Ukraine "Kyiv Polytechnic Institute", heat-and-power engineering department, sib-department of nuclear power stations and engineering thermal physics, specialty «Nuclear Power» Politehnichna st. 6, №5, Kyiv, Ukraine, 03055, Ukraine https://orcid.org/0000-0002-5733-5691

DOI:

https://doi.org/10.15587/2313-8416.2014.33717

Keywords:

reactor vessel, surveillance specimens, radiation embrittlement, brittleness critical temperature, dose dependence

Abstract

The analysis of measures aimed at improving the reliability of the test results of surveillance specimens that are used in the assessment of radiation embrittlement of materials of reactor vessels is done. It is demonstrated the effect of the realized measures to change of the dose dependence of the transition temperature of the material SUNPP-1 and RNPP-3 on the basis of experimental data.

Author Biographies

Виталий Георгиевич Ковыршин, NPP Operation Support Institute N.Vasilenko Street, 7, Kyiv, Ukraine, 03124

PhD (Technical Sciences), senior research fellow, leading research fellow

Department extend the life of nuclear power plants

Александр Владимирович Сахно, State scientific and technical center for nuclear and radiation safety V.Stusa Street, 35/37, Kyiv, Ukraine, 03142

PhD (Technical Sciences), head of the laboratory analysis of NPP equipment qualification and lifetime extension

References

PNAE G-7-008-89 "Rules of construction and safe operation of equipment and pipelines of nuclear power plants" (1990). Mosocw: Energoatomizdat, 141.

PNAEG-7-002-86 "Standards based on the strength of the equipment and pipelines of nuclear power plants" (1989). Moscow: Energoatomizdat, 525.

PM-T.0.03.120-08 "Typical properties of metal control program VVER-1000 samples-witnesses" (2008). Kiev NAEC "Energoatom", 33.

Vishnevsky, I. N., Vlasenko, N. I., Circo, L. I. et al (2011). Introduction of technology reconstruction witness samples metal VVER-1000 INR NAS. Problems of Atomic Science and Technology, 2, 54–58.

Kovyrshin, V. G., Grinik, E. W., Revka, V. N., Chirco, L. I., Tchaikovsky, Y. V. (2007). Comparison of the results of tests of samples witnesses staff and upgrade kit unit № 2 South-Ukrainian NPP. Proc. rep. V intern. scientific and engineering. conf. Russia (Podolsk), 109.

Vlasenko, N. I., Zinchenko, O. J., Kolochko, V. N., Simonov, I. M., Grebenuk, Y. P. (2005). The integrated program of witness samples for Ukrainian NPPs. Problems of Atomic Science and Technology, 5, 76–79.

US code of federal regulation, Nuclear Regulatory Commission, Part 50 (10CFR50)– Domestic licensing of production and utilization facilities, Appendix H – Reactor vessel material surveillance program requirements. Available at: http://www.law.cornell.edu/cfr/text/10/part-50

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Published

2014-12-22

Issue

Vol. 5 No. 2(5) (2014)

Section

Technical Sciences

License

Copyright (c) 2014 Виталий Георгиевич Ковыршин, Александр Владимирович Сахно, Валентина Александровна Григорьева

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