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CASCADE/INPE code system

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Abstract

The CASCADE/INPE code system, developed jointly by the Joint Institute of Nuclear Search and IATÉ, is intended for calculating the transport of charged particles and neutrons in the energy range from several GeV down to thermal energy in media with a complicated geometry and composition. It includes as individual blocks the CASCADE and MCNP-4B programs and an interface-program. The CASCADE block is used to model the interaction of charged particles with target nuclei and particle transport in the medium at energies greater than a fixed cutoff energy (20 MeV for neutrons). Transport of neutrons with energy below 20 MeV is modeled using the MCNP-4B block. The interface program is intended for processing computational results using the CASCADE block and preparation of initial data for the MCNP-4B block.

An example of the calculation of the characteristics of a subcritical reactor with an external neutron source is presented, 1 figure, 6 references.

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References

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Translated from Atomnaya Énergiya, Vol. 87, No. 4, pp. 283–286, October, 1999.

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Barashenkov, V.S., Konobeev, A.Y., Korovin, Y.A. et al. CASCADE/INPE code system. At Energy 87, 742–744 (1999). https://doi.org/10.1007/BF02673263

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  • DOI: https://doi.org/10.1007/BF02673263

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