Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor

The purpose of this study was to examine the combined effect of enriching U-235 fuel and fuel fingers (Kernell) to determine its criticality (Keff). In this study, simulation of HTR (High Temperature Reactor) type reactors using MCNPX (Monte Carlo N eXtended Particles). The fuel used is UO2 which ha...

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Main Authors: E. Setiawati, Z. Arifin, N.A.K Umiati, S. Juliawan, F Arianto, A. Margiantono
Format: Article
Language:English
Published: EDP Sciences 2020-01-01
Series:E3S Web of Conferences
Online Access:https://www.e3s-conferences.org/articles/e3sconf/pdf/2020/62/e3sconf_icenis2020_10001.pdf
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spelling doaj-44efc624b1074c30b228f18f9fca5ae72021-04-02T16:45:43ZengEDP SciencesE3S Web of Conferences2267-12422020-01-012021000110.1051/e3sconf/202020210001e3sconf_icenis2020_10001Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature ReactorE. Setiawati0Z. Arifin1N.A.K Umiati2S. Juliawan3F Arianto4A. Margiantono5Physics Department, Faculty of Sciences and Mathematics, Diponegoro UniversityPhysics Department, Faculty of Sciences and Mathematics, Diponegoro UniversityPhysics Department, Faculty of Sciences and Mathematics, Diponegoro UniversityPhysics Department, Faculty of Sciences and Mathematics, Diponegoro UniversityPhysics Department, Faculty of Sciences and Mathematics, Diponegoro UniversityElectrical Engineering Semarang Privat UniversityThe purpose of this study was to examine the combined effect of enriching U-235 fuel and fuel fingers (Kernell) to determine its criticality (Keff). In this study, simulation of HTR (High Temperature Reactor) type reactors using MCNPX (Monte Carlo N eXtended Particles). The fuel used is UO2 which has a density of 10.4 gr / cm3, with impurity using 4 ppm Boron atom with Atomic B-10 fraction of 80.1% and B-11 of 19.9%. The variation of enrichment used is 7% to 15% and the fuel radius (Kernell) ranges from 160 µm to 340 µm. From the results, it was obtained that the optimum Keff occurs at 7% enrichment and the radius of the fuel of 310 µm was 1.01236.https://www.e3s-conferences.org/articles/e3sconf/pdf/2020/62/e3sconf_icenis2020_10001.pdf
collection DOAJ
language English
format Article
sources DOAJ
author E. Setiawati
Z. Arifin
N.A.K Umiati
S. Juliawan
F Arianto
A. Margiantono
spellingShingle E. Setiawati
Z. Arifin
N.A.K Umiati
S. Juliawan
F Arianto
A. Margiantono
Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
E3S Web of Conferences
author_facet E. Setiawati
Z. Arifin
N.A.K Umiati
S. Juliawan
F Arianto
A. Margiantono
author_sort E. Setiawati
title Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
title_short Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
title_full Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
title_fullStr Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
title_full_unstemmed Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor
title_sort simulation of fuel ball dimensional size and uranium enhancement for high temperature reactor
publisher EDP Sciences
series E3S Web of Conferences
issn 2267-1242
publishDate 2020-01-01
description The purpose of this study was to examine the combined effect of enriching U-235 fuel and fuel fingers (Kernell) to determine its criticality (Keff). In this study, simulation of HTR (High Temperature Reactor) type reactors using MCNPX (Monte Carlo N eXtended Particles). The fuel used is UO2 which has a density of 10.4 gr / cm3, with impurity using 4 ppm Boron atom with Atomic B-10 fraction of 80.1% and B-11 of 19.9%. The variation of enrichment used is 7% to 15% and the fuel radius (Kernell) ranges from 160 µm to 340 µm. From the results, it was obtained that the optimum Keff occurs at 7% enrichment and the radius of the fuel of 310 µm was 1.01236.
url https://www.e3s-conferences.org/articles/e3sconf/pdf/2020/62/e3sconf_icenis2020_10001.pdf
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