Development of a new deuterium-deuterium (D-D) neutron generator for prompt gamma-ray neutron activation analysis

K Bergaoui; N Reguigui; C K Gary; C Brown; J T Cremer; J H Vainionpaa; M A Piestrup

doi:10.1016/j.apradiso.2014.09.004

Development of a new deuterium-deuterium (D-D) neutron generator for prompt gamma-ray neutron activation analysis

Appl Radiat Isot. 2014 Dec:94:319-327. doi: 10.1016/j.apradiso.2014.09.004. Epub 2014 Sep 28.

Authors

K Bergaoui¹, N Reguigui², C K Gary³, C Brown³, J T Cremer³, J H Vainionpaa³, M A Piestrup³

Affiliations

¹ 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.
² 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.
³ Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, CA 94063, USA.

PMID: 25305524
DOI: 10.1016/j.apradiso.2014.09.004

Abstract

A new deuterium-deuterium (D-D) neutron generator has been developed by Adelphi Technology for prompt gamma neutron activation analysis (PGNAA), neutron activation analysis (NAA), and fast neutron radiography. The generator makes an excellent fast, intermediate, and thermal neutron source for laboratories and industrial applications that require the safe production of neutrons, a small footprint, low cost, and small regulatory burden. The generator has three major components: a Radio Frequency Induction Ion Source, a Secondary Electron Shroud, and a Diode Accelerator Structure and Target. Monoenergetic neutrons (2.5MeV) are produced with a yield of 10(10)n/s using 25-50mA of deuterium ion beam current and 125kV of acceleration voltage. The present study characterizes the performance of the neutron generator with respect to neutron yield, neutron production efficiency, and the ionic current as a function of the acceleration voltage at various RF powers. In addition the Monte Carlo N-Particle Transport (MCNP) simulation code was used to optimize the setup with respect to thermal flux and radiation protection.

Keywords: Deuterium–deuterium fusion reaction; MCNP; Neutron generator; Neutron yield; PGNAA; Shielding.