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Neutron-physical and heat-engineering aspects of uranium-graphite reactors loaded with enriched-uranium fuel elements

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References

  1. A. S. Zaimovskii, V. V. Kalashnikov, and I. S. Golovnin, Fuel Elements of Nuclear Reactors, Atomizdat, Moscow (1966).

    Google Scholar 

  2. L. Petrie and N. Landers, KENO V.a: An Improved Monte Carlo Criticality Program with Supergrouping, US Department of Energy (2000).

  3. N. N. Ponomarev-Stepnoi, G. L. Lunin, A. G. Morozov, et al., “VVÉR-T light-water thorium reactor,” At. Énerg., 85, No. 4, 263–271 (1998).

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Translated from Atomnaya Énergiya, Vol. 101, No. 2, pp. 153–155, August, 2006.

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Artel’nyi, Y.A., Gavrilov, P.M. & Tsyganov, A.A. Neutron-physical and heat-engineering aspects of uranium-graphite reactors loaded with enriched-uranium fuel elements. At Energy 101, 606–610 (2006). https://doi.org/10.1007/s10512-006-0138-9

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  • DOI: https://doi.org/10.1007/s10512-006-0138-9

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