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Yamauchi, Michinori*; Ochiai, Kentaro; Morimoto, Yuichi*; Wada, Masayuki*; Sato, Satoshi; Nishitani, Takeo
Radiation Protection Dosimetry, 116(1-4), p.542 - 546, 2005/12
Times Cited Count：3 Percentile：23.72(Environmental Sciences)no abstracts in English
Yamauchi, Michinori*; Sato, Satoshi; Nishitani, Takeo; Kawasaki, Hiromitsu*
Proceedings of 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE 2005) (CD-ROM), 4 Pages, 2005/09
no abstracts in English
Sasa, Toshinobu; Oigawa, Hiroyuki; Tayama, Ryuichi*; Hayashi, Katsumi*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.30 - 33, 2004/03
The construction of Transmutation Experimental Facility (TEF) is planned under the framework of Japan Proton Accelerator Research Complex (J-PARC) project. A liquid lead-bismuth (Pb-Bi) spallation target with beam power of 600MeV-200kW will be installed into the TEF. Analyses were performed to determine the effective thickness of biological shield for Pb-Bi target by using both MCNPX and ATRAS code system. Thickness of around 6m should be required to decrease the radiation level. The streaming analyses through the proton injection beam duct and the primary cooling circuit piping were also performed. The result of the beam duct streaming shows good agreement between the results of MCNPX and DUCT-III. The additional shield must be installed to suppress the activation of accelerator components. In the case of streaming through the primary cooling circuit piping, it is proved that the radiation level at the exit of the shield is allowable. The radiation level can be much more reduced by optimizing the bending position and length of the piping.
Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03
In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.
Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Hayashi, Katsumi*; Shin, Kazuo*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.46 - 49, 2004/03
A simple design code for duct-streaming radiations, DUCT-III was applied to the analyses of the streamed neutron spectra measured at TIARA labyrinth with two bends. The code satisfactorily reproduced the measured neutron energy spectra and the Monte Carlo calculations, except that every calculation overestimated the measured thermal components by factor of 2 or 3.
Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*; Hirayama, Hideo*; Shin, Kazuo*
JAERI-Tech 2003-018, 42 Pages, 2003/03
no abstracts in English
Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo; Nakano, Hideo*; Tayama, Ryuichi*
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1268 - 1271, 2002/08
no abstracts in English
Sasamoto, Nobuo; Nakashima, Hiroshi; Hirayama, Hideo*; Shibata, Tokushi*
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1264 - 1267, 2002/08
no abstracts in English
