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Fission converter and metal–oxide–semiconductor field effect transistor study of thermal neutron flux distribution in an epithermal neutron therapy beam
Author(s) -
Kaplan Greg I.,
Rosenfeld Anatoly B.,
Allen Barry J.,
Coderre Jeffrey A.,
Liu Hungyan B.
Publication year - 1999
Publication title -
medical physics
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.473
H-Index - 180
eISSN - 2473-4209
pISSN - 0094-2405
DOI - 10.1118/1.598703
Subject(s) - neutron flux , neutron temperature , materials science , neutron , neutron cross section , neutron capture , neutron detection , nuclear physics , radiochemistry , physics , chemistry
The depth distribution of the thermal neutron flux is a major factor in boron neutron capture therapy (BNCT) in determining the efficiency of cell sterilization. In this paper the fission detector method is developed and applied to measure the in‐phantom thermal neutron flux depth distribution. Advantages of the fission detector include small size, direct measurement of thermal neutron flux in a mixed radiation field of BNCT beam, self‐calibration, and the possibility of on‐line measurement. The measurements were performed at epithermal a BNCT facility. The experimental results were compared with the thermal neutron flux calculated by the Monte Carlo method and found to be in good agreement.