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Radionuclide production using a fast flux reactor

Karelin1, Efimov, Filimonov

  • 1Russia State Scientific Centre, Research Institute of Atomic Reactors, Dimitrovgrad. kar@orip.niiar.simbirsk.su

Applied Radiation and Isotopes : Including Data, Instrumentation and Methods for Use in Agriculture, Industry and Medicine
|September 26, 2000
PubMed
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Large-scale production of key radionuclides like 89Sr, 32P, 35S, 117mSn, and 153Gd is achievable using the BOR-60 fast flux reactor, demonstrating its potential for radioisotope generation.

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.

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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.