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Preliminary neutronic study of actinide transmutation in a fast reactor

M. Williams, J. W. McAdoo, George Fergus Flanagan

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Abstract

Preliminary results are cited from a neutronic study of actinide recycle in a fast reactor, using an LMFBR model. The work was performed as part of a Chemical Technology Division program for assessing the merit of actinide transmutation as a means of waste disposal. Calculations were performed by coupling two-dimensional diffusion theory calculations with point-depletion recycle calculations. Cross sections were obtained from a ''preliminary'' version of ENDF/B-V. Results are given concerning the recycled-actinide equilibrium condition and the waste-actinide destruction rate. The effect of adding U-238 diluent to reduce power peaking is examined parametrically. The heterogeneous effects of placing an actinide target assembly in a fuel lattice are also examined.

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Preliminary results are cited from a neutronic study of actinide recycle in a fast reactor, using an LMFBR model. The work was performed as part of a Chemical Technology Division program for assessing the merit of actinide transmutation as a means of waste disposal. Calculations were performed by coupling two-dimensional diffusion theory calculations with point-depletion recycle calculations. Cross sections were obtained from a ''preliminary'' version of ENDF/B-V. Results are given concerning the recycled-actinide equilibrium condition and the waste-actinide destruction rate. The effect of adding U-238 diluent to reduce power peaking is examined parametrically. The heterogeneous effects of placing an actinide target assembly in a fuel lattice are also examined.

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Available abstract

Preliminary results are cited from a neutronic study of actinide recycle in a fast reactor, using an LMFBR model. The work was performed as part of a Chemical Technology Division program for assessing the merit of actinide transmutation as a means of waste disposal. Calculations were performed by coupling two-dimensional diffusion theory calculations with point-depletion recycle calculations. Cross sections were obtained from a ''preliminary'' version of ENDF/B-V. Results are given concerning the recycled-actinide equilibrium condition and the waste-actinide destruction rate. The effect of adding U-238 diluent to reduce power peaking is examined parametrically. The heterogeneous effects of placing an actinide target assembly in a fuel lattice are also examined.

Key concepts: Nuclear transmutation, Actinide, Nuclear engineering, Diluent, Waste management, Environmental science, Radiochemistry, Nuclear physics

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