Capture γ-Ray Dose Equivalent at Double-Bend Maze Entrance: Monte Carlo Simulation and Analytical Methods and Measurements
Abstract
Purpose: The production of the secondary neutron in the high-energy megavoltage medical accelerator machines has been extensively studied. In this study, MCNP5 MC code and two analytical methods, the proposed method and IAEA 47 proposed method were used to capture γ-ray dose equivalent calculation.
Materials and Methods: MCNP5 code of the MC simulation method was used for code calculation in this study. The main components of a Varian 2100Clinac were simulated as well as a 30×30×30 cm3 water phantom, in a Source to Surface Distance (SSD) of 100cm. Apparent neutron source strength (QN) was obtained using F1, *F8 tallies, and a small scoring cell at the isocenter with a mass equal to 0.625g.
Results:.QN was obtained as 1.25 n/Gy X for the simulated linac head and was used in the other calculations. In the simulated double-bend maze treatment room with first and second lengths of the maze as 7m and 3m, the proposed method calculated capture γ-ray dose with 6.2% and 60% differences compared with MC simulation and IAEA 47 methods, respectively.
Conclusion: We concluded that Ghiasi and Mesbahi's proposed method performed better in capturing γ-ray dose equivalent calculation compared to IAEA 47 report. The proposed method reduced the difference from 60% to 6.2%.
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11- M. Beigi, F. Afarande, and H. Ghiasi, "Safe bunker designing for the 18MV Varian 2100 Clinac: a comparison between Monte Carlo simulation based upon data and new protocol recommendations." Reports of Practical Oncology & Radiotherapy, vol. 21, no. 1, pp. 42-49, (2016).
12- A. Ghasemi-Jangjoo and H. Ghiasi, "Application of the phase-space distribution approach of Monte Carlo for radiation contamination dose estimation from the (n,γ), (γ,n) nuclear reactions and linac leakage photons in the megavoltage radiotherapy facility." Reports of Practical Oncology & Radiotherapy, vol. 25, no. 2, pp. 233-240, (2020).
13- A. Mesbahi, H. Ghiasi, and S. R. Mahdavi, "Photoneutron and capture gamma dose equivalent for different room and maze layouts in radiation therapy." Radiation protection dosimetry, vol. 140, no. 3, pp. 242-249, (2010).
14- NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, "Structural Shielding Design and Evaluation for Megavoltage X-ray and Gamma-Ray Radiotherapy Facilities." NCRP, Bethesda,151, (2005).
15- Kersey RW, "Estimation of neutron and gamma radiation doses in the entrance mazes of SL75-20 linear accelerator treatment rooms." Med Mundi, 24: 151–5, (1979).
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18- R. K. Wu and P. H. McGinley, "Neutron and capture gamma along the mazes of linear accelerator vaults." Journal of Applied Clinical Medical Physics, vol. 4, no. 2, pp. 162-171, (2003).
19- H. Ghiasi and A. Mesbahi, "A new analytical formula for neutron capture gamma dose calculations in double-bend mazes in radiation therapy." Reports of Practical Oncology & Radiotherapy, vol. 17, no. 4, pp. 220-225, (2012).
20- Walter EJ and et al, "Experimental and computational determination of neutron dose equivalent around radiotherapy accelerators.", 107ed pp. 225-232, (2003).
21- Hosein Ghiasi and Asghar Mesbahi, "Monte Carlo characterization of photoneutrons in the radiation therapy with high energy photons: a Comparison between simplified and full Monte Carlo models." Int-J-Radiat-Res, vol. 8, no. 3, pp. 187-193, (2010).
22- A. Ghasemi-Jangjoo and H. Ghiasi, "Application of the phase-space distribution approach of Monte Carlo for radiation contamination dose estimation from the (n,γ), (γ,n) nuclear reactions and linac leakage photons in the megavoltage radiotherapy facility." Reports of Practical Oncology & Radiotherapy, vol. 25, no. 2, pp. 233-240, (2020).
23- N. Hien Thi et al., "Measurement of neutron capture cross sections for the 174Yb(n,γ)175Yb reaction at thermal and epithermal energies." Radiation Physics and Chemistry, 110738, In press (2022).
24- P. D. Allen and M. A. Chaudhri, "Photoneutron Production and Dosimetry in Tissue During High Energy Bremsstrahlung Radiotherapy." Radiation protection dosimetry, vol. 23, no. 1-4, pp. 341-344, (1988).
25- A. Facure, A. X. Da Silva, and R. C. Falcão, "Monte Carlo simulation of scattered and thermal photoneutron fluences inside a radiotherapy room." Radiation protection dosimetry, vol. 123, no. 1, pp. 56-61, (2007).
26- J. C. Rivera, R. C. Falcão, and C. E. deAlmeida, "The measurement of photoneutron dose in the vicinity of clinical linear accelerators." Radiation protection dosimetry, vol. 130, no. 4, pp. 403-409, (2008).
27- S. M. Ghavami, A. Mesbahi, and E. Mohammadi, "The impact of automatic wedge filter on photoneutron and photon spectra of an 18-MV photon beam." Radiation protection dosimetry, vol. 138, no. 2, pp. 123-128, (2010).
28- M. Zabihzadeh, M. Ay, M. Allahverdi, A. Mesbahi, S. Mahdavi, and M. Shahriari, "Monte Carlo estimation of photoneutrons contamination from high-energy x-ray medical Accelerators in treatment room and maze: a Simplified model." Radiation protection dosimetry, vol. 135, pp. 21-32, (2009).
2- B. S. Ishkhanov and V. N. Orlin, "Semimicroscopic description of the giant dipole resonance." Physics of Particles and Nuclei, vol. 38, no. 2, pp. 232-254, (2007).
3- A. Zanini, E. Durisi, F. Fasolo, C. Ongaro, L. Visca, U. Nastasi, K. Burn, G. Scielzo, J. Adler, J. Annand, and G. Rosner, "Monte Carlo simulation of the photoneutron field in linac radiotherapy treatments with different collimation systems." Physics in medicine and biology, vol. 49, pp. 571-582, (2004).
4- NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, "RADIATION PROTECTION FOR PARTICLE ACCELERATOR FACILITIES." NCRP, Bethesda,144, (2005).
5- International Atomic Energy Agency, "RADIATION PROTECTION IN THE DESIGN OF RADIOTHERAPY FACILITIES." IAEA, Vienna,47, (2006).
6- P. D. Allen and M. A. Chaudhri, "Photoneutron Production and Dosimetry in Tissue During High Energy Bremsstrahlung Radiotherapy." Radiation protection dosimetry, vol. 23, no. 1-4, pp. 341-344, (1988).
7- A. Facure, A. X. Da Silva, and R. C. Falcão, "Monte Carlo simulation of scattered and thermal photoneutron fluences inside a radiotherapy room." Radiation protection dosimetry, vol. 123, no. 1, pp. 56-61, (2007).
8- A. Naseri and A. Mesbahi, "A review on photoneutrons characteristics in radiation therapy with high-energy photon beams." Reports of Practical Oncology & Radiotherapy, vol. 15, no. 5, pp. 138-144, (2010).
9- H. Ghiasi and A. Mesbahi, "Sensitization of the analytical methods for photoneutron calculations to the wall concrete composition in radiation therapy." Radiation Measurements, vol. 47, no. 6, pp. 461-464, (2012).
10- H. Ghiasi, "Monte Carlo characterizations mapping of the (γ,n) and (n,γ) photonuclear reactions in the high energy X-ray radiation therapy." Reports of Practical Oncology & Radiotherapy, vol. 19, no. 1, pp. 30-36, (2014).
11- M. Beigi, F. Afarande, and H. Ghiasi, "Safe bunker designing for the 18MV Varian 2100 Clinac: a comparison between Monte Carlo simulation based upon data and new protocol recommendations." Reports of Practical Oncology & Radiotherapy, vol. 21, no. 1, pp. 42-49, (2016).
12- A. Ghasemi-Jangjoo and H. Ghiasi, "Application of the phase-space distribution approach of Monte Carlo for radiation contamination dose estimation from the (n,γ), (γ,n) nuclear reactions and linac leakage photons in the megavoltage radiotherapy facility." Reports of Practical Oncology & Radiotherapy, vol. 25, no. 2, pp. 233-240, (2020).
13- A. Mesbahi, H. Ghiasi, and S. R. Mahdavi, "Photoneutron and capture gamma dose equivalent for different room and maze layouts in radiation therapy." Radiation protection dosimetry, vol. 140, no. 3, pp. 242-249, (2010).
14- NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS, "Structural Shielding Design and Evaluation for Megavoltage X-ray and Gamma-Ray Radiotherapy Facilities." NCRP, Bethesda,151, (2005).
15- Kersey RW, "Estimation of neutron and gamma radiation doses in the entrance mazes of SL75-20 linear accelerator treatment rooms." Med Mundi, 24: 151–5, (1979).
16- French RL and Well MB, "An angle dependent albedo for fast neutron refelectioncalculation.", 19 ed pp. 441-448, (1964).
17- McCall RC, Jenkins TM, and Shore RA, "Transport of accelerator produced neutrons in a concrete room.", 26 edpp. 1593-1597, (1979).
18- R. K. Wu and P. H. McGinley, "Neutron and capture gamma along the mazes of linear accelerator vaults." Journal of Applied Clinical Medical Physics, vol. 4, no. 2, pp. 162-171, (2003).
19- H. Ghiasi and A. Mesbahi, "A new analytical formula for neutron capture gamma dose calculations in double-bend mazes in radiation therapy." Reports of Practical Oncology & Radiotherapy, vol. 17, no. 4, pp. 220-225, (2012).
20- Walter EJ and et al, "Experimental and computational determination of neutron dose equivalent around radiotherapy accelerators.", 107ed pp. 225-232, (2003).
21- Hosein Ghiasi and Asghar Mesbahi, "Monte Carlo characterization of photoneutrons in the radiation therapy with high energy photons: a Comparison between simplified and full Monte Carlo models." Int-J-Radiat-Res, vol. 8, no. 3, pp. 187-193, (2010).
22- A. Ghasemi-Jangjoo and H. Ghiasi, "Application of the phase-space distribution approach of Monte Carlo for radiation contamination dose estimation from the (n,γ), (γ,n) nuclear reactions and linac leakage photons in the megavoltage radiotherapy facility." Reports of Practical Oncology & Radiotherapy, vol. 25, no. 2, pp. 233-240, (2020).
23- N. Hien Thi et al., "Measurement of neutron capture cross sections for the 174Yb(n,γ)175Yb reaction at thermal and epithermal energies." Radiation Physics and Chemistry, 110738, In press (2022).
24- P. D. Allen and M. A. Chaudhri, "Photoneutron Production and Dosimetry in Tissue During High Energy Bremsstrahlung Radiotherapy." Radiation protection dosimetry, vol. 23, no. 1-4, pp. 341-344, (1988).
25- A. Facure, A. X. Da Silva, and R. C. Falcão, "Monte Carlo simulation of scattered and thermal photoneutron fluences inside a radiotherapy room." Radiation protection dosimetry, vol. 123, no. 1, pp. 56-61, (2007).
26- J. C. Rivera, R. C. Falcão, and C. E. deAlmeida, "The measurement of photoneutron dose in the vicinity of clinical linear accelerators." Radiation protection dosimetry, vol. 130, no. 4, pp. 403-409, (2008).
27- S. M. Ghavami, A. Mesbahi, and E. Mohammadi, "The impact of automatic wedge filter on photoneutron and photon spectra of an 18-MV photon beam." Radiation protection dosimetry, vol. 138, no. 2, pp. 123-128, (2010).
28- M. Zabihzadeh, M. Ay, M. Allahverdi, A. Mesbahi, S. Mahdavi, and M. Shahriari, "Monte Carlo estimation of photoneutrons contamination from high-energy x-ray medical Accelerators in treatment room and maze: a Simplified model." Radiation protection dosimetry, vol. 135, pp. 21-32, (2009).
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| Issue | Vol 10 No 1 (2023) | |
| Section | Original Article(s) | |
| DOI | https://doi.org/10.18502/fbt.v10i1.11508 | |
| Keywords | ||
| Monte Carlo Capture Gamma-Ray Dose Equivalent Photon Neutron | ||
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How to Cite
1.
Eghdam-Zamiri R, Ghiasi H. Capture γ-Ray Dose Equivalent at Double-Bend Maze Entrance: Monte Carlo Simulation and Analytical Methods and Measurements. Frontiers Biomed Technol. 2022;10(1):21-26.
