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A study of the photoneutron dose equivalent resulting from a Saturne 20 medical linac using Monte Carlo method

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EN
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EN
High energy linacs have several advantages including lower skin dose and higher dose rate at deep sighted tumors. But, at higher energies photonuclear reactions produce neutron contamination. Photoneutron contamination has been investigated from the early days of modern linacs. However, more studies have become possible using Monte Carlo codes developed in recent years. The aim of this study was to investigate the photoneutron spectrum and dose equivalent produced by an 18 MV Saturne linac at different points of a treatment room and its maze. The MCNP4C code was used to simulate the transport of photoneutrons produced by a typical 18 MV Saturne linac. The treatment room of a radiotherapy facility in which a Saturne 20 linac is installed was modeled. Neutron dose equivalent was calculated and its variations at various distances from the center of the X-ray beam was studied. It was noted that by increasing the distance from the center of the beam, fast neutrons decrease rapidly, but thermal neutrons do not change significantly. In addition, the photoneutron dose equivalent was lower for smaller fields. The fast photoneutrons were not recorded in the maze. It can be concluded that the fast photoneutrons are highly attenuated by concrete barrier, while the slow photoneutrons are increased. In addition, increasing the X-ray field size increases the photoneutron dose equivalent around the treatment room and maze. It seems that the walls play an effective role in increasing the photoneutron dose equivalent.
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39--43
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Bibliogr. 13 poz., rys.
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autor
autor
autor
autor
  • Department of Medical Physics, Tarbiat Modares University, P. O. Box 14115-151, Tehran, Iran, Tel.: +98 21 88011001, Fax: +98 21 88006544, bijanhashemi@yahoo.com
Bibliografia
  • 1. Agosteo S, Foglio PA, Maggioni SV, Terrani S, Borasi G (1995) Radiation transport in a radiotherapy room.Health Phys 68:27−34
  • 2. Briesmeister JF (2000) Manual of MCNP-4CTM– a general Monte Carlo n-particle transport code. Los Alamos, New Mexico
  • 3. Carinou E, Kamenopoulou V (1999) Evaluation of neutron dose in the maze of medical accelerators. Med Phys 26:2520−2525
  • 4. Chibani O, Ma CM (2003) Photonuclear dose calculations for high-energy photon beams from Siemens and Varian linacs. Med Phys 30:1990−2000
  • 5. d’Errico F, Luszik-Bhadra M, Nath R, Siebert BRL, Wolf U (2001) Depth dose-equivalent energies of photoneutrons generated by 6−18 MeV X-ray beams for radiotherapy. Health Phys 80;1:4−113
  • 6. d’Errico F, Nath R, Tana L, Corzio G, Alberts WG (1997)In-phantom dosimetry and spectrometry of photoneutrons from an 18 MeV linear accelerator. Med Phys 25:1717−1724
  • 7. Facur A, Falcao RC, Silva AX, Crispim VR, Vitorelli JC (2005) A study of neutron spectra from medical linear accelerators. Appl Radiat Isot 62:69−72
  • 8. Followill DS, Stoval MS, Kry SF, Ibbott GS (2003) Neutron source strength measurements for Varian Siemens Elekta and General Electric linear accelerator. J Appl Clin Med Phys 4:189−194
  • 9. NCRP (1971) Protection against neutron radiation. NCRP Report 38, Scientific Committee 4 on Heavy Particles. National Council on Radiation Protection and Measurements, Bethesda, MD, USA
  • 10. NCRP (1976) Structural shielding design and evaluation for medical use of X-rays and gamma rays of energies up to 10 MeV. NCRP Report 49. National Council on Radiation Protection and Measurements, Bethesda, MD, USA
  • 11. NCRP (1984) Neutron contamination from medical accelerators. NCRP Report 79. National Council on Radiation Protection and Measurements, Washington DC, USA
  • 12. Sohrabi M, Mostofizadeh A (1999) Measurement of photoneutron dose in and out of high energy X-ray beam of a Saturne 20 medical linear accelerator by ECE polycarbonate detectors. Radiat Meas 31:479−482
  • 13. Tosi G, Torresin A, Agosteo S et al. (1991) Neutron measurements around medical electron accelerators by active and passive detection techniques. Med Phys 18;1:54−60
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ6-0011-0038
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