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Possibilities of Deep Burnup of Americium and Neptunium in the Core of a Fast Sodium Reactor

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Abstract

One-time deep burnup of actinides (up to burnup >90% h.a.) followed by burial in geological formations without reprocessing is of great interest. In this paper, a method is proposed for deep burnup of americium and neptunium in special assemblies, containing actinides in an inert (stone-like) matrix and a strong moderator (zirconium hydride). Placing ∼130 such assemblies into a BN-800 core with oxide fuel permits 90–95% h.a. burnup in a realistic time – 2–3 runs (2.5–3.5 yr). Such a reactor permits utilizing up to 110 kg of americium and neptunium per year.

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REFERENCES

  1. I. V. Bur'evskii, V. A. Eliseev, I. Yu. Krivitskii, et al., “Conceptual strudies of ROX-fuel use in fast sodium power preactors,” Preprint FÉI-2958 (2002).

  2. I. Yu. Krivitskii, A. V. Tikhomirov, and I. V. Bur'evskii, “Effect of taking account of the heterogeneous structure of irradiation systems with a moderator on the process of transmutation of actinides in a fast reactor,” in: DISNAI-2002, Visaginas, Latvia, July 1-7, 2003, pp. 181-190.

  3. V. I. Matveev, I. Yu. Krivitskii, V. A. Eliseev, et al., “Use of fast sodium reactors for effective utilization of plutonium and minor actinides,” in: Russian Science and Technology Forum on Nuclear Reactors Operating on Fast Neutrons, Obninsk, December 8-12, 2003, pp. 74-75.

  4. O. D. Kazachkovskii, V. I. Matveev, V. A. Eliseev, and A. M. Tsibulya, “Prospects for using MOX fuel in fast sodium-cooled reactors,” Russian Science and Technology Forum on Nuclear Reactors Operating on Fast Neutrons, Obninsk ibid., pp. 66-67.

  5. A. S. Sergin, “Abstract of the TRIGEKS computer code for a small-group neutron-physical calculation of reactors in a three-dimensional geometry,” Vopr.At.Nauk.Tekh., Ser.Fiz.Tekh.Yad.Reakt., No. 4(32), 34-36 (1983).

    Google Scholar 

  6. G. N. Manturov, M. N. Nikolaev, and A. M. Tsibulya, “BNAB-93 system of group constants,” Vopr.At.Nauk.Tekh., Ser.Yad.Konst., No. 1, 59-98 (1996).

  7. G. N. Manturov, M. N. Nikolaev, A. Yu. Polyakov, and A. M. Tsibulya, “Abstract of the CONSYST computer code,” Vopr.At.Nauk.Tekh., Ser.Yad.Konst., No. 2, 148-150 (1999).

  8. A. L. Kochetkov, “CARE computer code-calculation of the isotope kinetics and the radiation and ecological characteristics of nuclear fuel with irradiation and a holding period,” Preprint FÉI-2431b (1995).

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Authors and Affiliations

  1. State Science Center of the Russian Federation –, A. I. Leipunskii Physics and Power-Engineering Institute, Russia

    V. A. Eliseev & E. V. Poplavskaya

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  1. V. A. Eliseev
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  2. E. V. Poplavskaya
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Eliseev, V.A., Poplavskaya, E.V. Possibilities of Deep Burnup of Americium and Neptunium in the Core of a Fast Sodium Reactor. Atomic Energy 96, 170–176 (2004). https://doi.org/10.1023/B:ATEN.0000030918.36633.7d

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  • DOI: https://doi.org/10.1023/B:ATEN.0000030918.36633.7d

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