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EVKLID/V1 Modeling of a Lead-Cooled Reactor Core with Water Vapor Ingress into the Coolant

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This article is devoted to model calculations of a lead-cooled reactor core performed using the EVKLID/V1 code. The ingress of water vapor into the core is modeled for the stationary state of the reactor at the rated power capacity. The change in the reactivity and power at different mass flow of water vapor is analyzed. Baseline calculations performed using the MCU-FR code were performed in order to substantiate the correctness of the EVKLID/V1 neutron-physical characteristics when experimental data are lacking.

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Authors and Affiliations

  1. Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), Moscow, Russia

    D. A. Koltashev

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  1. D. A. Koltashev
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Correspondence to D. A. Koltashev.

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Translated from Atomnaya Énergiya, Vol. 128, No. 2, pp. 114–116, February, 2020.

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Koltashev, D.A. EVKLID/V1 Modeling of a Lead-Cooled Reactor Core with Water Vapor Ingress into the Coolant. At Energy 128, 125–128 (2020). https://doi.org/10.1007/s10512-020-00661-z

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  • DOI: https://doi.org/10.1007/s10512-020-00661-z

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