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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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.