Abstract:
:Expansion of accelerator technologies into different application areas brings the need for neutron-field measurements in their vicinity. The measurements of neutron energy spectra and neutron dose rates can be done with the aid of neutron multisphere spectrometers with passive neutron detectors. In addition to the usually used thermoluminescent detectors and gold activation foils, another activation material-indium-can be considered. This paper presents a design of such an indium-based neutron multisphere spectrometer. Its response matrix was calculated with Monte Carlo code MCNP5 in the energy interval from 0.001 eV to about 20 MeV. The response matrix was validated with an Am-Be standard neutron source. MAXED code was used for neutron energy spectra unfolding. The values of the neutron fluence rate and neutron ambient dose equivalent rate in a reference point were calculated. The properties and advantages of indium for use in neutron multisphere spectrometry are discussed.
journal_name
Radiat Prot Dosimetryjournal_title
Radiation protection dosimetryauthors
Vlk P,Pavlovic Mdoi
10.1093/rpd/ncx183subject
Has Abstractpub_date
2018-04-01 00:00:00pages
1-8issue
1eissn
0144-8420issn
1742-3406pii
4210246journal_volume
179pub_type
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