The MCB code for numerical modeling of Fourth Generation nuclear reactors

Authors

  • Mikolaj Oettingen AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy, Krakow
  • Jerzy Cetnar AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy, Krakow
  • Tomasz Mirowski The Mineral and Energy Economy Research Institute of the Polish Academy of Sciences, ul. Wybickiego 7, 31-261 Krakow

DOI:

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

Keywords:

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

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.

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Author Biography

Mikolaj Oettingen, AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy, Krakow

Assistant Professor, Faculty of Energy and Fuels, Department of Nuclear Energy

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Published

2015-12-31

How to Cite

Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modeling of Fourth Generation nuclear reactors. Computer Science, 16(4), 392. https://doi.org/10.7494/csci.2015.16.4.392

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Articles