A Monte Carlo simulation package, MCNPX version 2.6.0, has been used to evaluate the effect on the response of a spherical neutron detector utilising various numbers of point detectors on the surface of a spherical polyethylene structure which forms an instrument specifically designed for low radiation environments
In homeland security, neutron detection is used to prevent the smuggling of Special Nuclear Material...
We characterize a passive dosimeter capable of measuring both fast and thermal neutrons for ambiant ...
The development of neutron detectors makes extensive use of the predictions of detector response thr...
Simulations were performed using MCNP5 to optimize the geometry of a neutron spec-trometer. The cyli...
cited By 8International audienceIn the present work, the general purpose radiation transport MCNPX c...
Neutron dosimeters measure neutron doses but portable, real time, high efficiency, and gamma insensi...
In order to research the characteristics of minitype neutron reference radiation field regulated by ...
This paper presents the results of Monte Carlo calculations on the response functions of spherical m...
Many researches have been done to develop and improve the performance of personal (individual) dosim...
The response of a passive neutron monitor area has been calculated using the Monte Carlo code MCNP5....
Neutron irradiator facilities with Am-Be sources are worldwide available in order to perform neutron...
The neutron response matrix for a Bonner sphere spectrometric system with a 3.2 cm diameter 3He prop...
The response in terms of personal dose equivalent of a passive fast neutron dosimeter composed of a ...
The influence of some experimental factors on the measured quantities in neutron spherical-shell tra...
A passive neutron area monitor has been designed using Monte Carlo methods; the monitor is a polyeth...
In homeland security, neutron detection is used to prevent the smuggling of Special Nuclear Material...
We characterize a passive dosimeter capable of measuring both fast and thermal neutrons for ambiant ...
The development of neutron detectors makes extensive use of the predictions of detector response thr...
Simulations were performed using MCNP5 to optimize the geometry of a neutron spec-trometer. The cyli...
cited By 8International audienceIn the present work, the general purpose radiation transport MCNPX c...
Neutron dosimeters measure neutron doses but portable, real time, high efficiency, and gamma insensi...
In order to research the characteristics of minitype neutron reference radiation field regulated by ...
This paper presents the results of Monte Carlo calculations on the response functions of spherical m...
Many researches have been done to develop and improve the performance of personal (individual) dosim...
The response of a passive neutron monitor area has been calculated using the Monte Carlo code MCNP5....
Neutron irradiator facilities with Am-Be sources are worldwide available in order to perform neutron...
The neutron response matrix for a Bonner sphere spectrometric system with a 3.2 cm diameter 3He prop...
The response in terms of personal dose equivalent of a passive fast neutron dosimeter composed of a ...
The influence of some experimental factors on the measured quantities in neutron spherical-shell tra...
A passive neutron area monitor has been designed using Monte Carlo methods; the monitor is a polyeth...
In homeland security, neutron detection is used to prevent the smuggling of Special Nuclear Material...
We characterize a passive dosimeter capable of measuring both fast and thermal neutrons for ambiant ...
The development of neutron detectors makes extensive use of the predictions of detector response thr...
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