Determination of Neutron Fluxes at the Self-shielded PET Cyclotron and the Electron Liniac Apparatus of Tokushima University Hospital Using Activation Foil Method

DOI Web Site 1 Citations
  • SAKAMA Minoru
    Department of Radiologic Science and Engineering, School of Health Scieneces, The University of Tokushima
  • SAZE Takuya
    Radioisotope Center, The University of Tokushima
  • TANII Takashi
    Department of Radiologic Science and Engineering, School of Health Scieneces, The University of Tokushima
  • MAEZAWA Hiroshi
    Department of Radiologic Science and Engineering, School of Health Scieneces, The University of Tokushima
  • MAEDA Kouji
    SHI Accelerator Service Ltd.
  • SATO Kazuo
    Tokushima University Hospital
  • HONDA Eiichi
    Department of Oral and Maxillofacial Radiology, Division of Medico-Dental Dynamics and Reconstruction, Institute of Health Biosciences, The University of Tokushima
  • NISHITANI Hiromu
    Department of Radiology, Division of Medico-Dental Dynamics and Reconstruction, Institute of Health Biosciences, The University of Tokushima

Bibliographic Information

Other Title
  • 医療用自己遮蔽型PETサイクロトロン及び電子リニアックにおける中性子束の箔放射化法による測定
  • イリョウヨウ ジコ シャヘイガタ PET サイクロトロン オヨビ デンシ リニアック ニ オケル チュウセイシソク ノ ハク ホウシャカホウ ニ ヨル ソクテイ

Search this article

Abstract

Up till now, from a radiation safety management point of view, it has been discussed to construct guidelines on estimation of neutron fluxes produced via operating various medical small accelerators and to establish uniformly the clearance system related to having neutron activation effects into each accelerator facility.That is, it was the aim of this investigation to accumulate the data on estimation basis of neutron flux measurements at those medical small accelerators by an activation foil method.In this work, the neutron fluxes at the self-shielded PET cyclotron and the electron liniac apparatus of Tokushima University Hospital have been measured as the medical small accelerator.As a result, for the self-shielded PET cyclotron, it was found that the thermal neutron flux is (1.04±0.05) x107 cm-2s-1 and the fast neutron fluxes are distributed over the range 1x104 (the neutron energy En=9MeV) to 1x107 (En=1.5 MeV) cm-2s-1 into the radiation shelter, and while the thermal neutron fluxes would be distributed over the range 5.0x101 to 9.9x101 cm-2s-1 and then the fast neutron dose leakages were not detected outside there. For the 6/10 MV electron liniac apparatus, it was also found that nearly the same thermal neutron fluxes would be distributed all around the liniac room and those measured values are over the range (1.01±0.18) x103 to (1.32±0.10) x103cm-2s-1.

Journal

Citations (1)*help

See more

Keywords

Details 詳細情報について

Report a problem

Back to top