This paper presents a new technique for the analysis of neutron pulse height distributions generated in an organic scintillation detector. The methodology presented can be applied to techniques such as neutron spectrum unfolding, which have a variety of applications, including nuclear nonproliferation and homeland security. The technique is based on two independent approaches: (i) the use of the MCNP-PoliMi code to simulate neutron detection on an event-by-event basis with the Monte Carlo method and (ii) an analytical approach for neutron slowing down and detection processes. We show that the total neutron pulse height response measured by the organic scintillators is given by the sum of a large number of different neutron histories, each c...
One particular purpose of nuclear safeguards, in addition to accounting for known materials, is the ...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...
This paper presents a new technique for the analysis of neutron pulse height distributions generated...
We describe the use of the MCNP-PoliMi code to simulate, on an event-by-event basis, the detection o...
Abstract. In this paper, we describe an event-by-event analysis of neutron detection in organic scin...
Organic scintillators, in both liquid and plastic form, are commonly used in systems for the detecti...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
Capture-gated neutron detectors are the object of recent investigations in the fields of nuclear saf...
Neutron coincidence counting is an established, non-destructive method for the qualitative and quant...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
A calculation of neutron detection efficiencies has been performed for organic scintillators using t...
In organic scintillators, the energy distribution of gamma rays and neutrons is indirectly measured ...
One particular purpose of nuclear safeguards, in addition toaccounting for known materials, is the d...
One particular purpose of nuclear safeguards, in addition to accounting for known materials, is the ...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...
This paper presents a new technique for the analysis of neutron pulse height distributions generated...
We describe the use of the MCNP-PoliMi code to simulate, on an event-by-event basis, the detection o...
Abstract. In this paper, we describe an event-by-event analysis of neutron detection in organic scin...
Organic scintillators, in both liquid and plastic form, are commonly used in systems for the detecti...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
Capture-gated neutron detectors are the object of recent investigations in the fields of nuclear saf...
Neutron coincidence counting is an established, non-destructive method for the qualitative and quant...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
We develop a fully analytic and self-contained description of the amplitude distribution of light pu...
A calculation of neutron detection efficiencies has been performed for organic scintillators using t...
In organic scintillators, the energy distribution of gamma rays and neutrons is indirectly measured ...
One particular purpose of nuclear safeguards, in addition toaccounting for known materials, is the d...
One particular purpose of nuclear safeguards, in addition to accounting for known materials, is the ...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...
A simulation based on the Monte Carlo method is described which has been performed using MCNPX 2.6.0...