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Computational modeling of the accident in the fourth power-generating unit of the chernobyl nuclear power plant

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Literature Cited

  1. E. Danilova, L. Podiazov, V. Trekhov, et al., "Experience and perspectives of the development of common 3-D dynamics code complex for large power reactors safety problem," IAEA Techn. Com. Meeting on Safety of RBMK Reactors, Vienna, April 6–10 (1992), p. 211.

  2. E. P. Velikhov, N. N. Ponomarev-Stepnoi, V. G. Asmolov, et al., "Current ideas about the appearance and development of the Chernobyl accident," in: Selected Works of the International Conference on "Nuclear Accidents and the Future of Power Generation. The Lessons of Chernobyl," Paris (1991, April 15–17), p. 12.

  3. P. Chan and A. Dastur, "The sensitivity of positive scram reactivity neutronic decoupling in the RBMK-1000," Nucl. Sci. Eng.,103, 289 (1989).

    Google Scholar 

  4. P. Loizzo, "2-D and 3-D neutron calculations during the Chernobyl transient," ENEA-RDIPE Rep. FT-WAA-00008 (1991).

  5. P. Loizzo, "Xe distribution effect on the initial power distribution of the Chernobyl accident," ENEA-RDIPE Rep. FT-WAA-00009 (1992).

  6. E. O. Adamov, V. P. Vasilevskii, A. I. Ionov, et al., "Analysis of the first phase of the Chernobyl accident," At. Énerg.,64, No. 1, 24 (1988).

    Google Scholar 

  7. A. A. Abagyan, I. M. Arshavskii, V. M. Dmitriev, et al., "Computational analysis of the initial stage of the Chernobyl accident," At. Énerg.,71, No. 4, 275 (1991).

    Google Scholar 

  8. E. Danilova, N. Zinovjeva, L. Podiazov, et al., "Problems of the creation of the full-scale computer code complex TROJA for RBMK-type reactor NPP's simulation. RBMK Safety—bilateral ENEA-RDIPE agreement on the dynamics modelling under severe accidents," 2nd Bilateral ENEA-RDIPE Working Meeting, Rome, May 20–25 (1990).

  9. T. Fowler, D. Vondy, and G. Cunningham, "Nuclear reactor core analysis: CITATION," ORNL-TM-2496, Rev. 2, Oak Ridge (1971).

  10. I. Stenbock, M. Rozhdestvensky, L. Podiazov, et al., "Methodology and code to calculate two group macro cross sections in RBMK reactor polycell," ET 91/03, Moscow (1991).

  11. I. Ya. Emel'yanov, V. V. Postnikov, Yu. I. Volod'ko, et al., "Monitoring and regulation of the energy distribution in RBMK reactors," At. Énerg.,48, No. 6, 360 (1980).

    Article  Google Scholar 

  12. L. L. Bronitskii, V. V. Postnikov, V. A. Ioshin, et al., "Reconstruction of the three-dimensional energy-release field in the RBMK-1500 fuel assemblies," At. Énerg.,70, No. 4, 246 (1991).

    Google Scholar 

  13. P. Loizzo, "RBMK super cell: void effect and control rod worth. A benchmark evaluation," ENEA-RDIPE Rep. FT-WAA-00005 (1991).

  14. P. Loizzo, "Alternate calculation of RBMK control rod worth. Addendum to the benchmark evaluation," ENEA-RDIPE Rep. FT-WAA-00006 (1991).

  15. P. Loizzo, "Qualification and adjustment of WIMS cross section for Chernobyl," ENEA-RDIPE Rep. FT-WAA-00007 (1991).

  16. M. I. Rozhdestvenskij, O. E. Gusejnova, V. K. Davydov, and L. V. Tochenyi, "Neutronics calculation of two-dimensional polylattices and reactivity effects of channel-type water-graphite reactors," 2nd Bilateral ENEA-RDIPE Working Meeting, Rome, May 20–25 (1990).

  17. V. Trekhov and L. Podlazov, "Automatic CITATION input for the RBMK polycell microscopic cross section model," ENEA-RDIPE Rep. FT-WAA-00015 (1992).

  18. P. Loizzo, L. Podlazov, and V. Trekhov, "Space discretization on RBMK with polycell physical constants," ENEA-RDIPE Rep. FT-WAA-00017 (1992).

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Scientific Research and Design Institute of Electrotechnical Machinery. ENEA, Italy. Translated from Atomnaya Énergiya, Vol. 77, No. 2, pp. 93–100, August, 1994.

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Podlazov, L.N., Trekhov, V.E., Cherkashov, Y.M. et al. Computational modeling of the accident in the fourth power-generating unit of the chernobyl nuclear power plant. At Energy 77, 580–587 (1994). https://doi.org/10.1007/BF02407430

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