scholarly journals Environmental assessment of the thermal neutron activation explosive detection system for concourse use at US airports

1990 ◽  
Author(s):  
C.G. Jones
Keyword(s):  
Neutron Activation ◽  
Thermal Neutron ◽  
Environmental Assessment ◽  
Detection System ◽  
Thermal Neutron Activation ◽  
Explosive Detection

Explosive detection system based on thermal neutron activation

1989 ◽  
Vol 4 (12) ◽  
pp. 17-20 ◽  
Author(s):  
T. Gozani ◽  
P. Ryge ◽  
P. Shea ◽  
C. Seher ◽  
R.E. Morgado
Keyword(s):  
Neutron Activation ◽  
Thermal Neutron ◽  
Detection System ◽  
Thermal Neutron Activation ◽  
Explosive Detection

Explosive detection system based on thermal neutron activation

2005 ◽  
Author(s):  
T. Cozani ◽  
P. Ryge ◽  
P. Shea ◽  
C. Seher ◽  
R.E. Morgado
Keyword(s):  
Neutron Activation ◽  
Thermal Neutron ◽  
Detection System ◽  
Thermal Neutron Activation ◽  
Explosive Detection

Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

2016 ◽  
Vol 2 (3) ◽  
Author(s):  
Zafar Ullah Koreshi ◽  
Hamda Khan
Keyword(s):  
Genetic Algorithm ◽  
Optimal Design ◽  
Neutron Activation ◽  
Thermal Neutron ◽  
Detection System ◽  
Neutron Transport ◽  
Thermal Neutron Activation ◽  
Design Parameters ◽  
Optimization Analysis ◽  
Mc Simulation

An optimal design analysis is carried out for an explosives’ detection system (EDS) based on thermal neutron activation (TNA) of a sample under investigation. The objective of this work is to use a genetic algorithm (GA) to obtain the optimized moderator design that would yield the “best” signal in a detection system. In a preliminary analysis, a full Monte Carlo (MC) simulation is carried out to estimate the effectiveness of various moderators, namely, water, graphite, and beryllium with respect to radiative capture (n,γ) reactions in a sample under investigation. Since MC simulation is computationally “expensive,” it is generally not used for random-search-based optimization analysis. Thus, more efficient methods are required for the design of optimal nuclear systems, where neutron transport is accurately modeled and iteratively solved for estimating the effect of independent design parameters. This paper proposes a computational scheme in which GA is coupled with the two-group neutron diffusion equation (DE) for carrying out an optimization analysis. The coupled GA-DE optimization scheme is demonstrated for obtaining the optimal moderator design. It is found that with considerably less computational effort than in an elaborate MC computation, the GA-DE approach can be used for the optimal design of detection systems.

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