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  1. No Access

    Article

    Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel

    OpenMC is a state-of-the-art Monte Carlo neutron transport simulation code that uses the Python programming language as an API. OpenMC supports eight burnup simulation algorithms. This study presents the resul...

    H. A. Tanash, D. A. Solovyov, V. G. Zimin, A. L. Lobarev… in Physics of Atomic Nuclei (2023)

  2. No Access

    Article

    Method for Determining the Time to Attaining the Minimum Controlled Power Level for VVER

    Reactor startup to the minimum controlled level (MCL) of power is one of the most hazardous nuclear operations in the service life of the reactor. Currently, codes for neutronic calculations such as reactor si...

    A. I. Al-Shamayleh, D. A. Solovyov, A. A. Semyonov… in Physics of Atomic Nuclei (2022)

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    Article

    Estimates of the Flow Rate of Pure Condensate when Reactor Plant WWER-1200 is Brought to the Minimum Controlled Power Level after the Emergency Protection Triggering

    Activation of the emergency protection entails the injection of a boric acid solution into the reactor core to the standstill value, after which the control rods are raised, and then it is possible to obtain p...

    A. I. Al-Shamayleh, D. A. Solovyov, A. A. Semenov… in Physics of Atomic Nuclei (2022)