Assessment of dosimetric characteristics of neutron radiation generated by medical linear accelerator of electrons
DOI:
https://doi.org/10.33408/2519-237X.2017.1-3.299Keywords:
medical electron linac, Monte-Carlo modelling, bremsstrahlung radiation, neutrons, radiation dose, beam therapy, MCNPAbstract
Purpose. The paper is aimed to study the neutron radiation from medical linear accelerators of high-energy electrons.
Methods. Mathematical modelling of coupled electron-photon and coupled photon-neutron transport was carried out. The calculations were performed using Monte-Carlo simulation.
Findings. Spectra of neutrons in the bunker were calculated. The average energy of neutrons from the head of linear accelerator varies depending on the measurement point. The approximate energy of source neutrons is 0,5 MeV. Scattering from the walls adds a significant part of thermal neutrons to the spectrum. The average energy of neutrons in the maze and outside the procedure room of the bunker is 0,025 eV.
Application field of research. The obtained results of this study could be used in the design of shielding of medical linear accelerators of electrons with energies above 10 MeV.
Conclusions. Although the standard shielding from X-ray radiation from medical linear accelerators is effective for neutron radiation, high-energy electrons produce neutrons that require better shielding to protect doctors and members of public.
References
Ma A. Monte Carlo study of photoneutron production in the Varian Clinac 2100C linac. Journal of Radioanalytical and Nuclear Chemistry. 2008. Vol. 276. No. 1. Pp. 119-123.
Zabihinpoor S. Calculation of Neutron Contamination from Medical Linear Accelerator in Treatment Room. Adv. Studies Theor. Phys. 2011. Vol. 5. No. 9. Pp. 421-428.
Neutron Contamination from Medical Electron Accelerators. Recommendations of the National Council on Radiation Protection and Measurements. NCRP Report No. 79. Bethesda, MD. 1995. 132 p.
Publikatsiya 103 Mezhdunarodnoy Komissii po radiatsionnoy zashchite (MKRZ) [Publication 103 of the International Commission on Radiological Protection. ICRP]. International Commission on Radiological Protection ; Transl. from Engl. Eds. M.F. Kiseljov and N. K. Shandala. Moscow: OOO PKF Alana, 2009. 344 p. (rus)
Donahue R.J., Nelson W.R. Distribution of Induced Activity in Tungsten Targets. SLAC-PUB-4728. Stanford: Stanford Linear Accelerator Center, 1988. 11 p.
Bednarz B.P. Detailed Varian Clinac accelerator modeling for calculating intermediate- and low-level non-target organ doses from radiation treatments. PhD thesis. Troy, 2008. 144 p.
Tiegel G. Specifikacii dlja modelej uskoritelej Klinak 2100C, 2100C/D & 2300 C/D. [Specifications for accelerator models Clinac 2100C, 2100C/D & 2300 C/D]. G. Tiegel. 2011.
Chu T.-C. The measurement of photoneutron in the vicinity of Siemens Primus Linear Accelerator. IRPA-10: 10. international congress of the International Radiation Protection Association. Hiroshima, 2000, available at: http://www.irpa.net/irpa10/cdrom/00101.pdf (acessed: May 02, 2017).
Briesmeister J.F. Ed. MCNP-A General Monte Carlo N-Particle Transport Code, Version 4B2. Los Alamos, NM: Los Alamos National Laboratory. 1997. 736 p.
Kuten' S.A. and oth. Primenenie metodov Monte-Karlo v reshenii zadach radiacionnoj zashhity i jadernoj bezopasnosti [Application of Monte-Carlo Methods to the Solution of Radiation Protection and Nuclear Safety Problems]. Fundamental'nye i prikladnye fizicheskie issledovaniya. 2010-2016 gg. Minsk: Izd. centr BGU, 2016. 424 p.
Petoussi-Henss N. and oth. International Commission on Radiological Protection. Conversion coefficients for radiological protection quantities for external radiation exposures. ICRP Publication 116. Ed. C.H. Clement. Pergamon Press, 2010. 257 p. (Annals of the ICRP).
Published
How to Cite
License
Copyright (c) 2017 Verenich K.A., Kuten' S.A., Khrushchinskiy A.A., Makarevich K.O., Minenko V.F.
CC «Attribution-NonCommercial» («Атрибуция — Некоммерческое использование») 4.0
