Exploration of Adiabatic Resonance Crossing Through Neutron Activator Design for Thermal and Epithermal Neutron Formation in 99Mo Production and Bnct Applications Publisher Pubmed



Khorshidi A¹
Source: Cancer Biotherapy and Radiopharmaceuticals Published:2015

Abstract

A feasibility study was performed to design thermal and epithermal neutron sources for radioisotope production and boron neutron capture therapy (BNCT) by moderating fast neutrons. The neutrons were emitted from the reaction between 9Be, 181Ta, and 184W targets and 30 MeV protons accelerated by a small cyclotron at 300μA. In this study, the adiabatic resonance crossing (ARC) method was investigated by means of 207Pb and 208Pb moderators, graphite reflector, and boron absorber around the moderator region. Thermal/epithermal flux, energy, and cross section of accumulated neutrons in the activator were examined through diverse thicknesses of the specified regions. Simulation results revealed that the 181Ta target had the highest neutron yield, and also tungsten was found to have the highest values in both surface and volumetric flux ratio. Transmutation in the 98Mo sample through radiative capture was investigated for the natural lead moderator. When the sample radial distance from the target was increased inside the graphite region, the production yield had the greatest value of activity. The potential of the ARC method is a replacement or complements the current reactor-based supply sources of BNCT purposes. © Mary Ann Liebert, Inc. 2015.