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The Medical Radiology and Radiation Safety journal ISSN 1024-6177 was founded in January 1956 (before December 30, 1993 it was entitled Medical Radiology, ISSN 0025-8334). In 2018, the journal received Online ISSN: 2618-9615 and was registered as an electronic online publication in Roskomnadzor on March 29, 2018. It publishes original research articles which cover questions of radiobiology, radiation medicine, radiation safety, radiation therapy, nuclear medicine and scientific reviews. In general the journal has more than 30 headings and it is of interest for specialists working in thefields of medicine¸ radiation biology, epidemiology, medical physics and technology. Since July 01, 2008 the journal has been published by State Research Center - Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency. The founder from 1956 to the present time is the Ministry of Health of the Russian Federation, and from 2008 to the present time is the Federal Medical Biological Agency.
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Medical Radiology and Radiation Safety. 2026. Vol. 71. № 4
DOI:10.33266/1024-6177-2026-71-4-133-138
G.A. Krusanov, Yu.E. Smirnov, A.V. Belousov, M.A. Kolyvanova
ON THE PROSPECTS OF USING THE DOMESTIC MONTE CARLO PARTICLE TRANSPORT CODE FOR DOSIMETRIC PLANNING OF BORON-NEUTRON CAPTURE THERAPY
A.I. Burnazyan Federal Medical Biophysical Center, Moscow, Russia
Contact person: M.A. Kolyvanova, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
ABSTRACT
Purpose: To compare the results of calculations of the radiation field characteristics of the domestic CMK code for particle transport using the Monte-Carlo method and Geant4 as applied to boron neutron capture therapy (BNCT, neutron energies 1–30 keV).
Material and methods: To evaluate the accuracy of the CMK code for BNCT, we calculated dose point kernels and absorbed dose distributions in a heterogeneous medium with inserts containing 10B. A comparison was made with the Geant4 software code.
Results: Dose distribution calculations using the Geant4 and CMK software codes were performed for neutron energies of 1–30 keV in a homogeneous aqueous medium. Good agreement between the results is observed, with the discrepancy not exceeding 1.5%. Absorbed dose distributions in a heterogeneous medium with a tumor-simulating insert with a 10B concentration of 500 μg/g (insert density of 1 g/cm3) for neutrons with energies from 1 to 30 keV in Geant4 and СMK showed deviations of no more than 10% in the region before the insert and a slightly smaller deviation in the insert region.
Conclusion: Taking into account the coincidence of dose point kernels and the fact that deviations in a heterogeneous medium do not exceed 10%, coupled with the far from perfect experimental base for measuring the absorbed dose created by neutron sources, it can be summarized that the CMK code is suitable for research in the field of BNCT.
Keywords: CMK code, Geant4, Monte Carlo, BNCT, absorbed dose distribution
For citation: Krusanov GA, Smirnov YuE, Belousov AV, Kolyvanova MA. On the Prospects of Using The Domestic Monte Carlo Particle Transport Code for Dosimetric Planning of Boron-Neutron Capture Therapy. Medical Radiology and Radiation Safety. 2026;71(4):133–138. DOI:10.33266/1024-6177-2026-71-4-133-138
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PDF (RUS) Full-text article (in Russian)
Conflict of interest.The authors declare no conflict of interest.
Financing. This study was conducted within the framework of the scientific program of the National Center for Physics and Mathematics, section №9.
Contribution. Article was prepared with equal participation of the authors.
Article received: 20.03.2026. Accepted for publication: 25.04.2026.