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Monte Carlo simulation of explosive detection system based on a Deuterium-Deuterium (D-D) neutron generator.
Bergaoui, K; Reguigui, N; Gary, C K; Brown, C; Cremer, J T; Vainionpaa, J H; Piestrup, M A.
Affiliation
  • Bergaoui K; Unité de recherche "Maîtrise et Développement des Techniques Nucléaires à Caractère Pacifique", National Center of Nuclear Sciences and Technologies, Technopole Sidi Thabet, BP 72-CP 2020, Tunisia. Electronic address: kaouther.bergaoui@cnstn.rnrt.tn.
  • Reguigui N; Unité de recherche "Maîtrise et Développement des Techniques Nucléaires à Caractère Pacifique", National Center of Nuclear Sciences and Technologies, Technopole Sidi Thabet, BP 72-CP 2020, Tunisia.
  • Gary CK; Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.
  • Brown C; Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.
  • Cremer JT; Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.
  • Vainionpaa JH; Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.
  • Piestrup MA; Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.
Appl Radiat Isot ; 94: 118-124, 2014 Dec.
Article in En | MEDLINE | ID: mdl-25154568
ABSTRACT
An explosive detection system based on a Deuterium-Deuterium (D-D) neutron generator has been simulated using the Monte Carlo N-Particle Transport Code (MCNP5). Nuclear-based explosive detection methods can detect explosives by identifying their elemental components, especially nitrogen. Thermal neutron capture reactions have been used for detecting prompt gamma emission (10.82MeV) following radiative neutron capture by (14)N nuclei. The explosive detection system was built based on a fully high-voltage-shielded, axial D-D neutron generator with a radio frequency (RF) driven ion source and nominal yield of about 10(10) fast neutrons per second (E=2.5MeV). Polyethylene and paraffin were used as moderators with borated polyethylene and lead as neutron and gamma ray shielding, respectively. The shape and the thickness of the moderators and shields are optimized to produce the highest thermal neutron flux at the position of the explosive and the minimum total dose at the outer surfaces of the explosive detection system walls. In addition, simulation of the response functions of NaI, BGO, and LaBr3-based γ-ray detectors to different explosives is described.
Key words

Full text: 1 Collection: 01-internacional Database: MEDLINE Type of study: Diagnostic_studies Language: En Journal: Appl Radiat Isot Journal subject: MEDICINA NUCLEAR / SAUDE AMBIENTAL Year: 2014 Document type: Article

Full text: 1 Collection: 01-internacional Database: MEDLINE Type of study: Diagnostic_studies Language: En Journal: Appl Radiat Isot Journal subject: MEDICINA NUCLEAR / SAUDE AMBIENTAL Year: 2014 Document type: Article