Medical Radiology and Radiation Safety. 2026. Vol. 71. № 3

DOI:10.33266/1024-6177-2026-71-3-128-134

O.A. Kochetkov¹, E.Yu. Tarasova², S.M. Shinkarev¹, E.A. Rumyantsev²,

Yu.D. Udalov¹

Comparison of Individual Emergency Neutron Radiation Dosimeters Used in the Organizations of Rosatom State Corporation Under a Spontaneous Chain Reaction

¹ A.I. Burnazyan Federal Medical Biophysical Center, Moscow, Russia

² Russian Federal Nuclear Center VNIIEF, Nizhny Novgorod region, Sarov, Russia

Contact person:  S.M. Shinkarev, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.

 

Abstract

Purpose: To assess the current state of reliability of the results of measurements of the absorbed dose of neutron radiation in an emergency exposure situation of workers and to produce recommendations for corrective actions aimed at providing a unified approach to carry out emergency dosimetric monitoring of external exposure based on reviewing and discussing the results of comparison tests of neutron radiation dosimetric systems used in organizations of the Rosatom State Corporation. 

Results: All measuring instruments presented in comparison tests are in the State Register of Measuring Instruments and comply with modern requirements for individual dosimetric monitoring systems. The criteria selected to assess the results of measurements of the absorbed dose of neutron radiation fully comply with the requirements of the interstate standardization system and the state system for provision of the uniformity of measurements. Based on the results of the analysis of the measurements of absorbed dose of neutron radiation carried out by the dosimeters DINA, DVGN-01 and Kordon-A, the estimates of the measuring capabilities of the methods applied in emergency dosimetric monitoring systems were obtained. The use of individual dosimeters with an extended upper limit of the range of measuring the individual dose equivalent of neutron radiation without taking into account the peculiarities of recording the absorbed dose can lead to a systematic shift in the measurement results, as demonstrated by such a measuring instrument as DVGN-01.

Conclusion: Modern requirements for dosimetric systems for individual emergency dosimetric monitoring of workers are necessary to be developed. The verification procedure for measuring instruments used for emergency dosimetric monitoring is needed to be determined, because at present there are no standards for the absorbed dose of neutron radiation in tissue (tissue kerma), as well as certified reference fields for the absorbed dose of neutron radiation. 

In order to solve a problem to objectively apply a specific measuring instrument to measure the absorbed dose of neutron radiation, the radiation safety services of organizations are recommended to:

− organize and conduct a special research aimed at determination of the characteristics of radiation fields at workplaces using radiometric and spectrometric methods;

− carry out experimental modeling of the procedure of external exposure to workers using anthropomorphic phantoms;

− determine correction coefficients for the individual dosimeters that are used. 

Keywords:  dosimeters, emergency dosimetric monitoring, comparison tests, spontaneous chain reaction, neutron radiation

For citation:  Kochetkov OA, Tarasova EYu, Shinkarev SM, Rumyantsev EA, Udalov YuD. Comparison of Individual Emergency Neutron Radiation Dosimeters Used in the Organizations of Rosatom State Corporation Under a Spontaneous Chain Reaction. Medical Radiology and Radiation Safety. 2026;71(3):128–134. DOI:10.33266/1024-6177-2026-71-3-128-134

 

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Conflict of interest. The authors declare no conflict of interest.

Financing. The study had no sponsorship.

Contribution. The article was prepared by one author.

Article received: 20.02.2026. Accepted for publication: 25.03.2026.