Please use this identifier to cite or link to this item:
https://hdl.handle.net/20.500.11851/7130
Title: | Neutronic Performance of New Coolants in a Fusion-Fission (hybrid) Reactor | Authors: | Übeyli, Mustafa | Keywords: | fissile fuel breeding fusion-fission hybrid reactor spent fuel tritium breeding |
Publisher: | Elsevier Science Sa | Abstract: | Selection of coolant used in the fuel zone of a fusion-fission (hybrid) reactor affects the neutronic performance of the blanket much. Recently, two coolants namely, Flinabe and Li20Sn80 have been investigated to use in fusion reactors as tritium breeder and energy carrier due to their advantages of low melting point, low vapor pressure. In this study, neutronic performance of these coolants in a hybrid reactor using Canada Deuterium Uranium Reactor (CANDU) spent fuel was investigated for an operation period of 48 months. And also that of natural lithium and Flibe was also examined for comparison. Neutron transport calculations were conducted on a simple experimental hybrid blanket in a cylindrical geometry 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. (C) 2004 Elsevier B.V. All rights reserved. | URI: | https://doi.org/10.1016/j.fusengdes.2004.07.017 https://hdl.handle.net/20.500.11851/7130 |
ISSN: | 0920-3796 |
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 |
Show full item record
CORE Recommender
SCOPUSTM
Citations
15
checked on Dec 21, 2024
WEB OF SCIENCETM
Citations
17
checked on Nov 2, 2024
Page view(s)
84
checked on Dec 23, 2024
Google ScholarTM
Check
Altmetric
Items in GCRIS Repository are protected by copyright, with all rights reserved, unless otherwise indicated.