Please use this identifier to cite or link to this item: https://hdl.handle.net/20.500.11851/7127
Title: Neutronic analysis of ARIES-RS fusion reactor fueled with thorium
Authors: Übeyli, Mustafa
Keywords: fissile fuel breeding
tritium breeding
energy multiplication
Issue Date: 2006
Publisher: Pergamon-Elsevier Science Ltd
Abstract: In this study, the neutronic performance of the ARIES-RS fusion reactor design using different types of thorium fuels, namely ThO2 or ThN dispersed in graphite or BeO, was investigated. Neutron transport calculations were conducted with the help of the SCALE4.3 system by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a S-8-P-3 approximation. Even though energy multiplication in the reactor was at low rates, a significant amount of fissile fuel U-233 was produced while providing sufficient tritium for the deuterium-tritium (DT) driver. Among the investigated fuel types, the blanket using ThN dispersed in a BeO matrix had the highest fissile fuel breeding values. (c) 2005 Elsevier Ltd. All rights reserved.
URI: https://doi.org/10.1016/j.enconman.2005.04.006
https://hdl.handle.net/20.500.11851/7127
ISSN: 0196-8904
Appears in Collections:Elektrik ve Elektronik Mühendisliği Bölümü / Department of Electrical & Electronics Engineering
Scopus İndeksli Yayınlar Koleksiyonu / Scopus Indexed Publications Collection
WoS İndeksli Yayınlar Koleksiyonu / WoS Indexed Publications Collection

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