- Tytuł:
- The MCB code for numerical modeling of Fourth Generation nuclear reactors
- Autorzy:
-
Oettingen, M.
Cetnar, J.
Mirowski, T. - Powiązania:
- https://bibliotekanauki.pl/articles/305705.pdf
- Data publikacji:
- 2015
- Wydawca:
- Akademia Górniczo-Hutnicza im. Stanisława Staszica w Krakowie. Wydawnictwo AGH
- Tematy:
-
Monte Carlo
nuclear reactors
radiation transport
MCB
VHTR
LFR - Opis:
- 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.
- Źródło:
-
Computer Science; 2015, 16 (4); 329-350
1508-2806
2300-7036 - Pojawia się w:
- Computer Science
- Dostawca treści:
- Biblioteka Nauki