منابع مشابه
A Novel Neutron Dosimeter
Background: Neutron contamination in our environment can cause harmful biological effects on human body. Therefore, many efforts have been made to construct a neutron dosimeter to estimate the received dose. Objective: To design a simple neutron dosimeter. Methods: The primary dosimeter had 3He as a spherical thermal neutron detector encircled by paraffin 10 cm in radius. Then, the paraffin sph...
متن کاملCompact thermal neutron sensors for moderator-based neutron spectrometers.
In the framework of the NESCOFI@BTF project of the Italian Institute of Nuclear Physics, different types of active thermal neutron sensors were studied by coupling semiconductor devices with a suitable radiator. The objective was to develop a detector of small dimensions with a proper sensitivity to use at different positions in a novel moderating assembly for neutron spectrometry. This work di...
متن کاملa novel neutron dosimeter
background: neutron contamination in our environment can cause harmful biological effects on human body. therefore, many efforts have been made to construct a neutron dosimeter to estimate the received dose. objective: to design a simple neutron dosimeter. methods: the primary dosimeter had 3he as a spherical thermal neutron detector encircled by paraffin 10 cm in radius. then, the paraffin sph...
متن کاملNeutron Moderator Development Research at the Low Energy Neutron Source
The Low Energy Neutron Source at Indiana University completed its construction phase roughly three years ago, and one of the more active research thrusts at the facility since that time has been our attempts to advance the state of the art in neutron moderation. This research program includes basic materials characterization, especially total neutron cross section measurements, as well as in-si...
متن کاملInvestigation of metal hydrides applicability as neutron moderator and shielding by MCNPX
In this research, the applicability of several metal hydrides as neutron moderator and shielding for D-D fusion sources has been investigated by MCNPX code. The results have been investigated in three steps to find the materials with lower thermal, fast and total neutron fluxes than conventional shielding materials. The results show relative advantages of LaNi5H6, VH, TiH2, TaH, Mg (BH4)2, YH2,...
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ژورنال
عنوان ژورنال: Nuclear Instruments and Methods
سال: 1959
ISSN: 0029-554X
DOI: 10.1016/0029-554x(59)90011-4