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- Title
A COMPARATIVE ANALYSIS OF GAS-COOLED FAST REACTOR USING HETEROGENEOUS CORE CONFIGURATIONS WITH THREE AND FIVE FUEL VARIATIONS.
- Authors
Prasetya, Fajri; Syarifah, Ratna Dewi; Karomah, Iklimatul; Aji, Indarta Kuncoro; Trianti, Nuri
- Abstract
GFR or Gas-cooled Fast Reactor is one type of fast generation-IV that uses a very high cooling temperature. Thus, it is necessary to have the right reactor core design so that the power distribution of neutrons produced reaches a safe and even limit point. The use of a uniform (homogeneous) reactor core can produce peaking power. This is very avoidable because it will cause a reactor accident. In this study, researchers tried to compare the results of the analysis for two heterogeneous reactor core designs including the configuration of 3 fuel variations and 5 fuel variations using UN-PuN fuel. This study aims to determine the keff value produced by both types of fuel variations during 5 years of burn-up and determine the characteristics of neutron flux, fission rate, and fission product during 15 years of burn-up. This study was started by calculating the homogeneous and heterogeneous core of 3 and 5 fuel variations with neutron transport simulation involving OpenMC. The calculation results show that the heterogeneous core configuration of 5 fuel variations for the keff value is more optimal than 3 fuel variations, because it has the smallest excess reactivity value. The neutron flux and fission rate characteristics for 5 fuel variations are more evenly distributed when compared to 3 fuel variations to maintain neutron lifetime and reactor life in operation. Burn-up residual plutonium material and minor actinide waste for 5 fuel variations have less mass than 3 fuel variations. The results of neutronic analysis of GFR reactors with heterogeneous reactor core designs for 5 fuel variations are better in terms of reactor criticality, neutron power distribution, and waste produced. Finally, optimization of the UN-PuN fuel volume fraction of 60 % provides the optimal keff value.
- Subjects
FAST reactors; FISSION products; NEUTRON flux; NUCLEAR reactor cores; NUCLEAR reactor accidents; WASTE products as fuel
- Publication
Eastern-European Journal of Enterprise Technologies, 2024, p6
- ISSN
1729-3774
- Publication type
Article
- DOI
10.15587/1729-4061.2024.298202