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Radiation Protection Dosimetry Advance Access originally published online on May 14, 2007
Radiation Protection Dosimetry 2007 126(1-4):652-656; doi:10.1093/rpd/ncm132
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© The Author 2007. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Neutron production in tissue-like media and shielding materials irradiated with high-energy ion beams

I. Gudowska1,*, M. Kopec2 and N. Sobolevsky3

1 Medical Radiation Physics, Karolinska Institutet and Stockholm University, Box 260, S-171 76 Stockholm, Sweden
2 Department of Theoretical and Computational Physics, AGH University of Science and Technology, Al. Mickiewicza 30, 30-059 Krakow, Poland
3 Department of Neutron research, Institute for Nuclear Research of the Russian Academy of Sciences, 117312 Moscow, Russia

* Corresponding author: irena.gudowska{at}ki.se

Secondary neutrons produced in high-energy therapeutic ion beams require special attention since they contribute to the dose delivered to patient, both to tumour and to the healthy tissues. Moreover, monitoring of neutron production in the beam line elements and the patient is of importance for radiation protection aspects around ion therapy facility. Monte Carlo simulations of light ion transport in the tissue-like media (water, A-150, PMMA) and materials of interest for shielding devices (graphite, steel and Pb) were performed using the SHIELD-HIT and MCNPX codes. The capability of the codes to reproduce the experimental data on neutron spectra differential both in energy and angle is demonstrated for neutron yield from the thick targets. Both codes show satisfactory agreement with the experimental data. The absorbed dose due to neutrons produced in the water and A-150 phantoms is calculated for proton (200 MeV) and carbon (390 MeV/u) beams. Secondary neutron dose contribution is ~0.6% of the total dose delivered to the phantoms by proton beam and at the similar level for both materials. For carbon beam the neutron dose contribution is ~1.0 and 1.2% for the water and A-150 phantoms, respectively. The neutron ambient dose equivalent, H*(10), was determined for neutrons leaving different shielding materials after irradiation with ions of various energies.


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