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Article title
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Abstract
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Keywords
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Introduction
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Recycle of fissile materials in the joint TR-FR system
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Specificity of neutron reactions in fast reactors with plutonium loading
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Specificity of neutron reactions in thermal reactors with uranium loading
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Use of FM fractions in reactors under operation in a partial refueling regime
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Numerical studies of the joint TR-FR system
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Mathematical model
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Algorithm of searching for fuel self-sufficiency conditions in the joint TR-FR system
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Neutron-physical analyses of the joint TR-FR system
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Conclusions
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Acknowledgements
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References
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