Precise Numerical Simulation of Gamma-ray Pulse Height Spectrum Measured with a CdTe Detector Designed for BNCT-SPECT

DOI Web Site 参考文献5件
  • NAKAMURA Soichiro
    Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University
  • MUKAI Taiki
    Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University
  • MANABE Masanobu
    Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University
  • MURATA Isao
    Division of Electrical, Electronic and Information Engineering, Graduate School of Engineering, Osaka University

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Boron neutron capture therapy (BNCT) is a new radiation therapy which can destroy tumor cells. In order to know the actual treatment effect directly in real time, we are developing a spectatorial system, which is called BNCT-SPECT. In the present study, we examined the feasibility of BNCT-SPECT by use of a CdTe detector taking into account the real BNCT scene. Precise calculations were carried out with MCNP5 to evaluate the pulse height spectra, which is to be measured by the CdTe detector. It was confirmed from the calculation results that at the energy of 478 keV, the S/N ratio is greater than unity and the number of counts exceeds 1000.

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