Radionuclide production using a fast flux reactor

Area of Science:

• Nuclear Chemistry
• Radiochemistry
• Reactor Physics

Background:

• Fast flux reactors offer unique neutron spectra for radionuclide production.
• Previous studies have explored various reactor types for radioisotope synthesis.

Purpose of the Study:

• To experimentally investigate the feasibility of producing specific radionuclides using the BOR-60 fast flux reactor.
• To evaluate the efficiency and yield of producing 89Sr, 32P, 35S, 117mSn, and 153Gd.

Main Methods:

• Irradiation of target materials (e.g., Gadolinium) within the BOR-60 reactor core and blanket.
• Utilizing (n, p) and (n, gamma) nuclear reactions for radionuclide synthesis.
• Analysis of radionuclide yield and specific activity after reprocessing.

Main Results:

• Successful production of 89Sr, 32P, 35S via (n, p) reactions and 117mSn, 153Gd via (n, gamma) reactions.
• Achieved high neutron flux (1 x 10^15 cm^-2 s^-1) for effective irradiation over 40-100 days.
• Demonstrated production of 153Gd in a softened neutron spectrum within the radial blanket.

Conclusions:

• The BOR-60 fast flux reactor is a viable platform for the large-scale production of the studied radionuclides.
• The reactor's capabilities support diverse production routes, including different neutron spectrum environments.
• Experimental data confirms the potential for efficient radioisotope generation for various applications.