Affiliation:
1. Cumhuriyet University, Technology Faculty, Department of Manufacturing Engineering, Sivas, Turkey
2. Erciyes University, Engineering Faculty, Department of Energy, Systems Engineering, Kayseri, Turkey
Abstract
Nuclear spent fuel management is one of the top major subjects in the
utilization of nuclear energy. Hence, solutions to this problem have been
increasingly researched in recent years. The basic aim of this work is to
examine the fissile breeding and transuranic fuel transmutation potentials of
a gas cooled accelerator-driven system. In line with this purpose, firstly,
the conceptually designed system is optimized by using several target
materials and fuel mixtures, from the point of neutronic. Secondly, three
different material compositions, namely, pure lead bismuth eutectic (LBE),
LBE+natural UO2, and LBE+15 % enrichment UO2, are considered as target
material. The target zone is separated to two sub-zones but as one within the
other. The outer sub-zone is pure LBE target, and the inner sub-zone is
either UO2 or pure LBE target. The UO2 target sub-zone is cooled with helium
gas. Finally, the thorium dioxide mixed with transuranic dioxides, discharged
from PWR-MOX spent fuel, in pebbles composed of graphite and TRISO-coated
spherical fuel particles, is used for breeding fissile fuel and transmuting
transuranic fuels. Three different thorium-transuranic mixtures, (Th, Pu)O2,
(Th, Cm)O2, (Th, Pu, MA)O2, are examined with various mixture fractions. The
packing fractions of the fuel pebbles in the transmutation core and the
tristructural-isotropic coated fuel particles in a pebble are assumed as 60 %
and 29 %, respectively. The transmutation core is also cooled with a
high-temperature helium coolant. In order to produce high-flux neutrons that
penetrate through the transmutation core, the target is exposed to the
continuous beams of 1 GeV protons. The computations have been carried out
with the high-energy Monte Carlo code MCNPX using the LA150 library. The
numerical outcomes show that the examined accelerator-driven system has
rather high neutronic data in terms of the energy production and fissile fuel
breeding.
Publisher
National Library of Serbia
Subject
Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Cited by
6 articles.
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