Design study of neutron beam facility around TRIGA research reactor core

Abstract Research reactors are used as neutron generators in contrast to power reactors in which energy production is the prime issue. To make neutrons available outside the reactor core, beam ports are designed around the core. These beam ports can be characterized by neutron flux level which is useful for neutron beam application in a reactor. The neutron and gamma flux variation was studied as a function of different orientations of beam tubes and optimally minimum information is produced to understand neutron beam design and use. An optimum core has been modeled based on TRIGA research reactor, defined as base model. Three optimal combinations of piercing, tangential and radial beam ports have been studied against the base model. Along with beam port characterization, the effect of beam ports on the core has been also studied in reverse in terms of reactivity variation and neutron flux distribution inside the core. Such characterization is useful where preliminary calculations are needed for avoiding detailed computer calculation to model the beam.