Background <p>Nuclear power waste can be reduced by replacing depleted uranium with spent nuclear fuel (SNF) from high-power channel (RBMK) reactors in the fuel compositions of fast neutron reactors.</p> Aim <p>To determine the possibility of using RBMK SNF, processed through a simplified reprocessing technique, as a&#xa0;feedstock for fast reactors.</p> Materials and methods <p>We have simulated a&#xa0;fuel campaign for a&#xa0;modernized 1200 MW BN-1200M sodium-cooled fast neutron reactor fueled with U‑Pu nitride fuel. Physical calculations were carried out for scenarios with both homogeneous and heterogeneous layouts of the fast reactor core; the layouts are planned to be used at the stage&#xa0;1 and stages&#xa0;2, 3 of operation, respectively.</p> Results <p>The results of physical calculations are presented for a&#xa0;scenario with a&#xa0;simplified technology of RBMK SNF reprocessing for the first active loading and makeup fuel: the maximum reactivity margin for the burnup of the core fuel has increased by 0.3&#xa0;and 0.4% for a&#xa0;homogeneous and heterogeneous layout, respectively. The equivalent dose rate (EDR) of photon radiation from the fresh fuel assembly similarly increases by ~250 and ~40&#xa0;times for a&#xa0;30-day and 3‑year storage, respectively. The EDR of fission products for a&#xa0;fresh assembly decreases to 70&#xa0;and 50&#xa0;μSv/h at a&#xa0;purification factor of 1·10<sup>4</sup> and its increased value, respectively.</p> Conclusion <p>Reprocessed RBMK SNF used instead of depleted uranium fully realizes the energy potential of natural uranium, as well as reduces nuclear power waste and load on SNF storage facilities.</p>

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Effects of spent nuclear fuel on neutron and physical characteristics of a fast reactor core

  • E. A. Rodina,
  • G. N. Vlaskin,
  • A. A. Kashirskii,
  • V. I. Rachkov

摘要

Background

Nuclear power waste can be reduced by replacing depleted uranium with spent nuclear fuel (SNF) from high-power channel (RBMK) reactors in the fuel compositions of fast neutron reactors.

Aim

To determine the possibility of using RBMK SNF, processed through a simplified reprocessing technique, as a feedstock for fast reactors.

Materials and methods

We have simulated a fuel campaign for a modernized 1200 MW BN-1200M sodium-cooled fast neutron reactor fueled with U‑Pu nitride fuel. Physical calculations were carried out for scenarios with both homogeneous and heterogeneous layouts of the fast reactor core; the layouts are planned to be used at the stage 1 and stages 2, 3 of operation, respectively.

Results

The results of physical calculations are presented for a scenario with a simplified technology of RBMK SNF reprocessing for the first active loading and makeup fuel: the maximum reactivity margin for the burnup of the core fuel has increased by 0.3 and 0.4% for a homogeneous and heterogeneous layout, respectively. The equivalent dose rate (EDR) of photon radiation from the fresh fuel assembly similarly increases by ~250 and ~40 times for a 30-day and 3‑year storage, respectively. The EDR of fission products for a fresh assembly decreases to 70 and 50 μSv/h at a purification factor of 1·104 and its increased value, respectively.

Conclusion

Reprocessed RBMK SNF used instead of depleted uranium fully realizes the energy potential of natural uranium, as well as reduces nuclear power waste and load on SNF storage facilities.