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(searched for: doi:10.4236/wjnst.2017.71002)
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S Tukiran, P Surian, Ph Endiah
Published: 1 February 2022
Abstract:
The safety calculation of the RSG-GAS reactor core needs to be done if new high-density fuel is used in the RSG-GAS core. The use of new high-density fuels is very much needed in the RSG-GAS core so that it is necessary to calculate its safety. When using high density fuel there will be a “bottle neck” effect where there is a problem with the fuel and cladding interaction. According to previous researchers this can be overcome by adding metal elements Si, Ni or Ti to fuel. However, with the addition of metal elements Si, Ni or Ti to the fuel, it needs to be analyzed in the RSG-GAS core. The analysis was carried out calculations using a computer program by simulating the Si metal used 1%, 2%, 3% 4% and 5% in the fuel. The calculation of the additional metal element in the high-density fuel effect on the reactivity of the RSG-GAS core was carried out with the WIMSD-5B and Batan-FUEL programs. The WIMSD-5B program is a computer program consisting of several modules including the transport module which is used for the calculation of the generation of macroscopic constants for the 19.75% enriched uranium silicide fuel and the density of 4.8 gU/cc as a function of degree of burn. Core calculations were performed using a neutron diffusion program, namely Batan-FUEL. By calculating the core criticality at operating temperature, the core neutronic parameter values are obtained. The results of the analysis show that the amount of Si 5% in the high density fuel matrix can solve the bottle neck problem and the neutronic parameters are still within the safety limit. This value will determine how much the value of the fuel burn up and control rods are in accordance with the acceptance criteria so that the safety analysis can be carried out on the RSG-GAS core using high density. From the analysis, it was found that the addition of the element Si in the high-density fuel matrix did not find any significant changes in core reactivity and neutronic parameter.
, P Surian, Y Farisy
Published: 1 March 2021
Journal of Physics: Conference Series, Volume 1811; https://doi.org/10.1088/1742-6596/1811/1/012047

Abstract:
The amount of thorium in the world is very abundant and the benefits of using thorium as fuel for nuclear reactors such as PWR are increasingly widespread, so it needs to be analyzed. In the initial phase, the PWR pin cell fuel analysis was carried out using the WIMSD-5B code. The PWR ThO2-UO2 fuel in the cladding with the fuel assembly model 17 x 17 is analyzed by its fuel burn up, neutron flux and isotope composition after maximum operation. The pin cell model consisting of fuel, cladding and coolant with a square pitch of 12.6 cm are calculated using different libraries. Eigenvalues, neutron fluxes and isotope concentrations were compared with the PWR pin cell model to high burnup. The eigenvalues and flux neutron as a function of burnup are good, the maximum difference is within 7.41% and the mean absolute difference is less than 3.12 %. The best comparison of fission product isotope concentrations is to use the ENDFB7.1 library with Thorium fuel and is comparable to the uranium fuel reported in the literature. Data sources for actinides and fission products used infuel depletion calculations for thorium fuel are all documented.
, Andrei Rykhlevskii, G.V. Tikhomirov, Kathryn D. Huff
Published: 14 December 2020
Annals of Nuclear Energy, Volume 152; https://doi.org/10.1016/j.anucene.2020.108035

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T Surbakti, P Surian, Y Farisy, M Imron
Published: 1 March 2020
Journal of Physics: Conference Series, Volume 1485; https://doi.org/10.1088/1742-6596/1485/1/012007

Abstract:
The RSG-GAS is using U3Si2-Al dispersion fuels with a uranium density of 2.96 gU/cc. The silicide uranium fuels are not used anymore for the future. To anticipate the usage of other fuels in the RSG-GAS core, UMo-Al fuels were chosen. The UMo-Al fuel has many advantages some of them, it can be used at a higher density in the reactor core. There are high uranium densities in UMo-Al dispersion fuels up to 16 gU/cm3 with numerous contents of Mo. In this analysis, the RSG-GAS core is used with a high density of UMo-Al fuel. The neutronic parameter is such as reactivity balances, keff, and power peaking factor and safety reactivity factor of UMo-Al fuel with higher density. The UMo-Al core criticality data are achieved by calculation using the Batan-FUEL code. The UMo-Al fuel macroscopic cross-section data as the output of cell calculation WIMSD-B5 (ENDFVII.0) were used for the calculation. The core calculations were performed using a 2 and 3 dimension diffusion code. The calculation results show that the good fuel for RSG-GAS is U7Mo-Al with maximum radial and axial power peaking factor of U7Mo-Al with high density at 20 cm control rod depth is 1.32 and 1.73 respectively and safety reactivity factor more than 1.5. The results show that all neutronic parameters are met the safety criteria. Hence U7Mo with higher density could be applied for RSG-GAS core and operated for 1500 MWD cycle length
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