Fabrication and calibration of new carbon-14 reference standards using irradiated graphite from uranium–graphite reactors

A. O. Pavliuk, S. G. Kotlyarevsky, R. I. Kan, V. B. Gorshkov, I. M. Maksimova, A. G. Volkova, E. V. Zakharova, A. V. Stepanov, A. G. Volkovich, Yu N. Simirsky, V. N. Dushin, I. E. Alekseev, V. G. Merkulov, E. V. Tchibisov, D. V. Kabanov

Research output: Contribution to journalArticlepeer-review

Abstract

The paper deals with measurements of carbon-14 in irradiated nuclear graphite. It suggests approaches to the problem, impart experience in production and calibration of new C-14, reference standards got from irradiated elements (sleeve, block) of the uranium–graphite reactor (UGR) stacks. Reference standards in the form of irradiated graphite were created and certified by the C-14 concentration. The concentration of C-14 in different samples was determined by interlaboratory comparisons. Results of the work proved an opportunity of creating reference materials for the C-14 radionuclide based on irradiated graphite obtained from the graphite elements of the uranium–graphite reactors. C-14 reference standards with different concentrations of interfering Cl-36, Co-60, H-3, Cs-137, Sr-90 and other radionuclides can be used for future development of new methods of determination the C-14 concentration in irradiated graphite and spectrometric equipment calibration.

Keywords

  • Application of reference standards
  • C-14 reference standard
  • Interlaboratory comparisons
  • Irradiated graphite
  • Measuring instrument

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Instrumentation

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