The MCB code for numerical modeling of Fourth Generation nuclear reactors

Mikolaj Oettingen, Jerzy Cetnar, Tomasz Mirowski

Abstract


R&D in the nuclear reactor physics demands state-of-the-art numerical tools that are able to characterize investigated nuclear systems with high accuracy. In this paper, we present the Monte Carlo Continuous Energy Burnup Code (MCB) developed at AGH University’s Department of Nuclear Energy. The code is a versatile numerical tool dedicated to simulations of radiation transport and radiation-induced changes in matter in advanced nuclear systems like Fourth Generation nuclear reactors. We present the general characteristics of the code and its application for modeling of Very-High-Temperature Reactors and Lead-Cooled Fast Rectors. Currently, the code is being implemented on the supercomputers of the Academic Computer Center (CYFRONET) of AGH University and will soon be available to the international scientific community.

Keywords


Monte Carlo; Nuclear Reactors; Radiation Transport; MCB; VHTR; LFR

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DOI: https://doi.org/10.7494/csci.2015.16.4.392

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