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Computational analysis of the effectiveness of the working elements of the safety and control system in a vpbér-600 core by means of engineering and precision programs

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References

  1. V. D. Sidorenko, S. P. Aver'yanova, V. V. Pshenin, and A. A. Suslov, “KASSETA-2 program for calculating the neutron-physical characteristics of heterogeneous fuel assemblies of reactors with light-water moderator,” Report No. 32/1-984-90, Institute of Atomic Energy (1990).

  2. E. D. Belyaeva, E. A. Zholkevich, L. V. Kokhanovskaya, et al., “Three-dimensional two-group sparse-matrix program — physical model of a VVÉR-reactor,” Report No. 1673 OFAP-YAR, Institute of Atomic Energy (1990).

  3. J. Brismeister (ed.), “A general Monte Carlo code for neutron and photon transport, Ver. 3A,” Rep. LA-7396-V Rev. 2, September (1986).

  4. R. MacFarlane, The NJOY Nuclear Data Processing System, Ver. 91.0.LA, February (1991).

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Authors
  1. R. A. Peskov
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  2. V. I. Alekseev
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  3. L. V. Levanov
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  4. O. B. Samoilov
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  5. E. F. Mitenkova
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  6. N. V. Novikov
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Additional information

Special Office of Machine Design Institute of Fast Reactors, Russian Academy of Sciences. Translated from Atomnaya Énergiya, Vol. 79, No. 3, pp. 171–174, September, 1995.

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Peskov, R.A., Alekseev, V.I., Levanov, L.V. et al. Computational analysis of the effectiveness of the working elements of the safety and control system in a vpbér-600 core by means of engineering and precision programs. At Energy 79, 579–583 (1995). https://doi.org/10.1007/BF02407407

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  • DOI: https://doi.org/10.1007/BF02407407

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