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Analysis of the neutron-physical characteristics of the fuel lattice of the VVÉR-1000 reactor

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References

  1. S. A. Astakhov, A. S. Dukhovenskii, Yu. A. Krainov, et al., “Results of studies of the reactivity coefficients of the VVÉR-1000 reactor core,” Vopr. At. Nauk Tekh. Ser. Fiz. Tekh. Yad. Reaktorov, No. 8, 69 (1987).

    Google Scholar 

  2. S. A. Astakhov, V. A. Voznesenskii, A. S. Dukhovenskii, et al., “Directions of optimization of cores of VVÉR-1000 reactor,” in: Proceedings of Eighteenth VMK Symposium on the Physics of VVÉR Reactors, Sept. 11–16, 1989, Czechoslovakia, Vol. 2.

  3. E. A. Kovshov, V. I. Pavlov, V. D. Sidorenko, et al., “Fuel cycles of the VVÉR-1000 reactor based on uranium-gadolinium fuel,” in: Proceedings of Eighteenth VMK Symposium on the Physics of VVÉR Reactors [in Russian], Vol. 2, September 11–16, 1989, Czechoslovakia.

  4. “Nuclear Safety Rules for Reactor Installations of Atomic Power Plants. Nuclear Safety Regulations PBYa RU AS-89,” At. Énerg.,69, No. 6, 409 (1990).

  5. Foreign Water-Moderated Water-Cooled Reactors and Their Fuel Cycle. Improvement of the Fuel for Water-Moderated Water-Cooled Reactors [in Russian], TsNIIatominform, No. 8, Moscow (1989).

  6. F. Skogen, J. Hulsman, and J. Gale, “Achieving two-year cycles in PWR's,” in: Proceedings of International Reactor Physics Conference, Jackson Hole, Wyoming (1988), pp. 1.109–1.118.

    Google Scholar 

  7. J. Secker, J. Pritchett, D. Chung, and H. Keller, “Design and Operational experience with Westinghouse ZrB2 integral burnable absorbers in advanced PWR fuel,” in: Proceedings of International Reactor Physics Conference, Jackson Hole, Wyoming (1988), pp. 1-135–1-148.

    Google Scholar 

  8. V. V. Saprykin, “Contents of model problem of neutron-physical calculations of a commercial VVÉR-1000 reactor with three-year refueling,” in: Proceedings of Eighteenth VMK Symposium on the Physics of VVÉR Reactors [in Russian], Vol. 2, September 11–16, 1989, Czechoslovakia.

  9. R. Jain, V. Jagannathan, P. Krishnani, and V. Jain, “Supershell model for PWR fuel-assembly burnup and analysis of IAEA PWR benchmark,” in: Proceedings of Technical Committee Meeting on In-Core Fuel Management, Vienna, IAEA (1989), pp. 272–281.

    Google Scholar 

  10. G. G. Bartomolei, G. A. Bat', V. D. Baibakov, and M. S. Alkhutov, Fundamentals of the Theory and Computational Methods for Nuclear-Power Reactors [in Russian], Énergoatomizdat, Moscow (1989).

    Google Scholar 

  11. A. D. Galanin, Introduction to the Theory of Thermal-Neutron Nuclear Reactors [in Russian], Énergoatomizdat, Moscow (1990).

    Google Scholar 

  12. V. D. Sidorenko and V. V. Pshenin, “Engineering methods and programs of preparation of small-group constants for calculations of reactor cores with light-water moderator,” Vopr. At. Nauk Tekh. Ser. Fiz. Tekh. Yad. Reaktorov., No. 4, 3 (1985).

    Google Scholar 

  13. A. N. Novikov, V. V. Pshenin, M. P. Lizorkin, et al., “Problems of VVÉR in-core fuel management,” in: Proceedings of Technical Committee Meeting on In-Core Fuel Management, Vienna, IAEA (1989), pp. 325–334.

    Google Scholar 

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Russian Scientific Center “Kurchatov Institute.” Translated from Atomnaya Énergiya, Vol. 74, No. 1, pp. 10–21, January, 1993.

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Pavlov, V.I. Analysis of the neutron-physical characteristics of the fuel lattice of the VVÉR-1000 reactor. At Energy 74, 9–18 (1993). https://doi.org/10.1007/BF00750968

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