Utilization of heavy metal molten salts in the ARIES-RS fusion reactor

被引:4
|
作者
Ubeyli, Mustafa [1 ]
Yapici, Hueseyin [2 ]
机构
[1] TOBB Ekon Teknol Univ, Muhendislik Fak, TR-06560 Sogutozu Ankara, Turkey
[2] Erciyes Univ, Muhendislik Fak, TR-38039 Kayseri, Turkey
关键词
heavy metal molten salt; fissile fuel breeding; tritium breeding;
D O I
10.1007/s10894-007-9129-7
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
ARIES-RS is one of the major magnetic fusion energy reactor designs that uses a blanket having vanadium alloy structure cooled by lithium [1, 2]. It is a deuterium-tritium (DT) fusion driven reactor, having a fusion power of 2170 MW [1, 2]. This study presents the neutronic analysis of the ARIES-RS fusion reactor using heavy metal molten salts in which Li(2)BeF(4) as the main constituent was mixed with increased mole fractions of heavy metal salt (ThF(4) or UF(4)) starting by 2 mol.% up to 12 mol.%. Neutron transport calculations were carried out with the help of the SCALE 4.3 system by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a S(8)-P(3) approximation. According to the numerical results, tritium self-sufficiency was attained for the coolants, Flibe with 2% UF(4) or ThF(4) and 4% UF(4). In addition, higher energy multiplication values were found for the salt with UF(4) compared to that with ThF(4). Furthermore, significant amount of high quality nuclear fuel was produced to be used in external reactors.
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页码:200 / 205
页数:6
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