Radiation quality and absorbed dose at different positions in the primary beam and around the shielding of a neutron generator
conference paper
A description of mixed neutron-gamma fields should include information on neutron and photon absorbed dose as well as radiation quality. For the actual set-up at our institute, the characteristics of the radiation fields were determined to assess the contribution of scatter from the walls of the irradiation room to the total absorbed dose and to evaluate the effectiveness of the protective shielding. Neutrons were produced by a Van de Graaff accelerator employing the d+T and d+D reactions. Lineal energy distributions were determined with a tissue equivalent (TE) proportional counter. Neutron energy spectra were measured with an organic liquid scintillator proton-recoil spectrometer. Neutron and gamma absorbed doses were derived from the responses of a TE ion chamber and a Geiger-Mueller counter and the dose equivalent was measured with a rem counter. Fractional dose and fractional fluence distributions were compared with respect to energy degradation of the produced neutrons. Mean quality factors and dose equivalent values were determined for different conditions.
Topics
Biological shieldingExperimental dataGamma dosimetryGraphsMicrodosimetryNeutron dosimetryNeutron fluenceNeutron sourcesRadiation dose distributionsRadiobiologyTablesVan De Graaff acceleratorsAcceleratorsBiologyDataData formsDosimetryElectrostatic acceleratorsInformationNumerical dataParticle sourcesRadiation sourcesShielding
TNO Identifier
353175
ISBN
0-906346-02-9
Publisher
International Atomic Energy Agency (IAEA)
Source title
6th Symposium on microdosimetry, 22-26 May 1978, Brussels, Belgium
Editor(s)
Booz, J.
Ebert, H.G.
Ebert, H.G.
Place of publication
Vienna
Pages
615-627
Files
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