The effect of 99mo production on the neutronic safety parameters of research reactors

Abstract EN

One of the main purposes of research reactors is the production of radioisotopes for medicine, industry and research activities.

99mTc is one of these radioisotopes, it is generated from the radioactive decay of 99Mo and it is supplied to hospitals as 99Mo/99mTc generators.

The most available and efficient route for obtaining the high specific activity 99Mo required for the 99mTc generators is the separation from fission products resulting from the irradiation of 235U targets in research reactors.

The aim of this paper is to present the neutronic calculations performed to study the effect of introducing an Irradiation Device for 99Mo Production into a research reactor core utilized for fuel irradiation.

Also the operational conditions with the presence of the irradiation device for 99Mo production from low enriched fuel irradiated in a research reactor are verified.

Calculations are carried out in order to evaluate all core neutronic parameters to assure that the core load satisfies all safety design criteria.