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Measurement of γ-ray dose in a thermal neutron field by using a 3He-filtered GM counter

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3 Author(s)
K. Kudo ; Electrotech. Lab., Ibaraki, Japan ; N. Takeda ; A. Fukuda

A new type of 3He-filtered GM counter has been used to measure the dose of γ-rays existing in a thermal neutron field. The detector assembly consists of a commercially available GM counter surrounded by a cylindrical aluminum vessel filled with 3He gas at a pressure up to 6 atmospheres. The contribution of secondary γ-rays produced by thermal neutron capture in the GM counter itself can be excluded by increasing the 3He pressure, because the thermal neutron capture reaction of 3He(n, p)T results in the emission of charged particles of a proton and a triton. In order to determine the response of the GM counter, the energy spectrum deposited in the counter gas to monoenergetic γ-rays was calculated by EGS4 Monte-Carlo code for a γ-ray energy range from 60 keV to 10 MeV and then the response was derived through calibration of the counter at γ-ray energies of 60 keV, 662 keV and 1.17 MeV+1.33 MeV. The γ-ray energy distribution in the thermal neutron field was obtained by an MCNP Monte-Carlo calculation, assuming a three dimensional experimental assembly of a graphite pile, which also included the concrete floor in the experimental room. The γ-ray fluence and the effective dose equivalent in the thermal neutron field have been determined by using the GM counter response, the γ-ray energy distribution in the field and the conversion factor from fluence to effective dose equivalent

Published in:

IEEE Transactions on Nuclear Science  (Volume:43 ,  Issue: 3 )