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Preliminary study on influence of changing void fraction (VF) on SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario for boiling water reactor (BWR) spent fuel direct recycling scheme has been carried out. Several VF values of BWR have been investigated to determine the criticality of reactor. The VF values range from 20% to 60%....
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... 2e5 show the effective multiplication factor for 20% void with 5% SF in loaded fuel, for 30% void with 10% SF in loaded fuel, for 50% void with 10% SF in loaded fuel, and for 60% void with 20% SF in loaded fuel, respectively. Table 4 gives the summary of required uranium enrichment to obtain the criticality condition of all evaluated VF values and SF fraction in loaded fuel. To gain the criticality condition, the required uranium enrichment should be raised with the augmenting of void fraction as well as the enhancing of the fraction of spent fuel in loaded fuel. ...
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... The nuclear energy program has not been able to be accepted openly by the world community due to the following 3 main reasons: 1) Fear of proliferation, 2) Fear of accidents such as Chernobyl and Three Mile Island, and 3) Nuclear waste management issues [4][5]. However, the true issue regarding nuclear energy acceptance is the long-lived high level nuclear waste (HLW) management [6][7], since some of radioisotopes in HLW have more There are several methods for dealing with HLW. One of them is by transmuting the long-lived nuclear waste into shorter life by using Accelerator Driven Subcritical System (ADS) [8][9][10][11] The Accelerator Driven Subcritical System is a system consisting of a subcritical nuclear reactor and a particle accelerator. ...
... than million year of half-lived. HLW consist of plutonium (Pu), minor actinides (MA), and long-lived fission products (LLFP)[6][7]. Energy consumption and CO2 emissions in the world from year 1990-2025[1] ...
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Analysis of the influence of void fraction distribution is very important to learn about the fission process and heat produced by the fuel assembly, here in this study several void fraction (VF) values along different burnup values have been considered in order to observe their influence in power distribution, uranium consumption, neutron flux andbehaviour for a GE-12 fuel assembly. For this study, burnups up to 60 MWd/kg and VF values up to 0.8 were considered setting the uranium enrichment at 3.5 weight percent at the start of every VF scenario, results show that higher void fractions reduce the thermal flux decreasing thermal fission and limiting heat production.
