Advanced Monte Carlo Calculations using MCNP of Ex-Vessel Neutron Dosimetry for Cycle 25 of Krško Nuclear Power Plant

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This repository includes calculation results of reaction rates for Ex-Vessel Neutron Dosimetry (EVND) program at the Krško nuclear power plant during 25th fuel cycle [1].

25th fuel cycle took place from October 25, 2010, to April 15, 2012.

Calculations were performed using Monte Carlo N-Particle transport code MCNP [2] in combination with the hybrid code ADVANTG [3] to speed up the convergance of the results outside the reactor core. Calculated reaction rates were normalized [4] to the nominal reactor power of 2 GW. Calculations were performed with the detailed geometrical model of the reactor core and detailed fixed neutron source modeled representing hot full power core state for the Krško NPP 25th fuel cycle [5], [6]. Detailed core model and fixed neutron source were included in the simplified geometrical model of the Krško NPP containment building [7].

A detailed description of the calculation procedure, calculation models, calculation results, experimental data and sensitivity studies is presented in the scientific paper:

T. Goričanec, B. Barbarič, V. Radulović, D. Čalič, L. Snoj and M. Kromar, "Advanced Monte Carlo Analysis of Ex-Vessel Neutron Dosimetry for Cycle 25 of Krško Nuclear Power Plant", to be sent for submission to Progress in Nuclear Energy, March 2025.