Abstract
Radiation shielding design of a cancer therapy facility using compact proton synchrotron was carried out. For bulk shielding calculation, the effective dose attenuation formula based on Moyer Model was used. Attenuation lengths used in the formula were derived by the one-dimensional discrete ordinate code ANISN using the DLC-119/HILO86 high-energy multi-group cross section library. For skyshine dose calculation, SHINE-III code was used. To calculate radiation streaming through mazes and ducts, Nakamura and Uwamino's formula and DUCT-III code were applied, respectively. As an emission of neutron by proton beam losses, measured neutron yield spectra of 256 MeV incident proton at LANL was used. To determine an emission of gamma ray by the beam losses, the FLUKA routine bundled in GEANT code was used. Results from the calculation satisfy the limits from the domestic law of the radiation protection. (author)
Makita, Yo;
Tsuchidate, Hiroyuki;
Yamazaki, Masaharu;
[1]
Nakamura, Takashi
[2]
- Mitsubishi Electric Corp., Amagasaki, Hyogo (Japan)
- Tohoku Univ., Cyclotron and Radioisotope Center, Sendai, Miyagi (Japan)
Citation Formats
Makita, Yo, Tsuchidate, Hiroyuki, Yamazaki, Masaharu, and Nakamura, Takashi.
Radiation shielding design of a cancer therapy facility using compact proton synchrotron.
Japan: N. p.,
2004.
Web.
Makita, Yo, Tsuchidate, Hiroyuki, Yamazaki, Masaharu, & Nakamura, Takashi.
Radiation shielding design of a cancer therapy facility using compact proton synchrotron.
Japan.
Makita, Yo, Tsuchidate, Hiroyuki, Yamazaki, Masaharu, and Nakamura, Takashi.
2004.
"Radiation shielding design of a cancer therapy facility using compact proton synchrotron."
Japan.
@misc{etde_20620304,
title = {Radiation shielding design of a cancer therapy facility using compact proton synchrotron}
author = {Makita, Yo, Tsuchidate, Hiroyuki, Yamazaki, Masaharu, and Nakamura, Takashi}
abstractNote = {Radiation shielding design of a cancer therapy facility using compact proton synchrotron was carried out. For bulk shielding calculation, the effective dose attenuation formula based on Moyer Model was used. Attenuation lengths used in the formula were derived by the one-dimensional discrete ordinate code ANISN using the DLC-119/HILO86 high-energy multi-group cross section library. For skyshine dose calculation, SHINE-III code was used. To calculate radiation streaming through mazes and ducts, Nakamura and Uwamino's formula and DUCT-III code were applied, respectively. As an emission of neutron by proton beam losses, measured neutron yield spectra of 256 MeV incident proton at LANL was used. To determine an emission of gamma ray by the beam losses, the FLUKA routine bundled in GEANT code was used. Results from the calculation satisfy the limits from the domestic law of the radiation protection. (author)}
place = {Japan}
year = {2004}
month = {Mar}
}
title = {Radiation shielding design of a cancer therapy facility using compact proton synchrotron}
author = {Makita, Yo, Tsuchidate, Hiroyuki, Yamazaki, Masaharu, and Nakamura, Takashi}
abstractNote = {Radiation shielding design of a cancer therapy facility using compact proton synchrotron was carried out. For bulk shielding calculation, the effective dose attenuation formula based on Moyer Model was used. Attenuation lengths used in the formula were derived by the one-dimensional discrete ordinate code ANISN using the DLC-119/HILO86 high-energy multi-group cross section library. For skyshine dose calculation, SHINE-III code was used. To calculate radiation streaming through mazes and ducts, Nakamura and Uwamino's formula and DUCT-III code were applied, respectively. As an emission of neutron by proton beam losses, measured neutron yield spectra of 256 MeV incident proton at LANL was used. To determine an emission of gamma ray by the beam losses, the FLUKA routine bundled in GEANT code was used. Results from the calculation satisfy the limits from the domestic law of the radiation protection. (author)}
place = {Japan}
year = {2004}
month = {Mar}
}