Developing a new target design for producing 99Mo in a MTR reactor.

Abstract

99Mo is an important radioisotope and mainly produced using uranium fission reaction in a nuclear reactor. Investigation for probable improvements, especially on target geometry and in-core location of target is the main goal of this research. This is for producing more efficient of 99Mo in a typical Material Testing Reactors (MTRs). A parametric investigation is done focused on the target characteristics such as geometry, location, material, density, heat flux (power density) and also usability in Tehran Research Reactor (TRR) as a MTR case study. Stochastic code MCNPX 2.6.0 along with CFD code ANSYS are used to perform neutronic and thermal-hydraulic analyses. A target with plate type design is specified and proposed as a final and most favorable design. Taking into account the safety criteria, the production yield, the chemical process and radioactive waste, it is demonstrated that the new target design meets the key design requirements without compromising the reactor safety. This research results indicate that the new target gives rise to a higher production of 99Mo using less amount of initial material causing to a reduction in nuclear waste and process difficulties.