Desain Konseptual Reaktor Cepat Berpendingin Karbondioksida dan Berbahan Bakar Uranium Alam Dengan Daya 2400 MW
Abstract
This paper presents the design concept of a carbon dioxide-cooled fast reactor. This reactor utilize U-10%Zr as fuel and SS316 as cladding. The strategy of modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production) was applied for burnup in the core with power 2400 MW. The reactor core calculations were performed with a cylindrical geometry that is varied on the height and diameter of the core using a set of CITATION and PIJ modules on the SRAC (Standard Reactor Analysis Code) program. The ideal core size was obtained with a high of 350 cm, and a diameter of 240 cm with the resulting survey parameter are effective multiplication factor(keff), excess reactivity, radial and axial power distribution, and power peaking. The reactor core reaches a critical condition with keff 1.05 and excess reactivity 5.3% and radial power peaking 1.73. Optimization was done with power flattening, that is by dividing the core into two parts with a fuel fraction of 60% for the inner part with thick of 80 cm and fuel fraction of 65% for the outer part with thick of 40 cm, the results are 1.013, 1.3% and 1.5 for keff, excess reactivity, and radial power peaking, respectively.
Keywords
Full Text:
PDF (Bahasa Indonesia)References
Ariani, M., Su’ud, Z., Monado, F., & Waris, A. (2013). Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input. Applied Mechanics and Materials, 260-261, 307-311.
Duderstadt, J., & Hamilton. (1976). Nuclear Reactor Analysis. New York: John Wiley & Sons.
Kuntoro, I. (2018). Keselamatan Reaktor Nuklir. Jakarta: BATAN.
Monado, F., Su’ud, Z., Waris, A., Basar, K., Ariani, M., & Sekimoto, H. (2013). Application of Modi¬fied CANDLE Burnup to Very Small Long Life Gas-cooled Fast Reactor. Advanced Materi¬als Research, 772, 501-506.
Okumura, K. (2007). Introduction of SRAC for Reactor Physics Analyses. Japan: JAEA.
Riska, Fitriyani, D., & Irka, F. H. (2016). Analisis Neutronik pada Gas Cooled Fast Reactor (GCFR) dengan Variasi Bahan Pendingin (He, CO2, N2). Jurnal Fisika Unand, 5(1), 28-34.
Sekimoto, H. (2001). The New Burnup Startegy. Nuclear Science and Engineering, 139, 306-317.
Stacey, W.M. (2007). Nuclear Reactor Physics. Willey-VCH: USA.
Surbakti & Purwadi. (2017). Karakteristik Reaktivitas Teras Kerja RSG-Gas Selama 30 Tahun Beroperasi. Jurnal Penelitian Fisika dan Aplikasinya (JPFA), 07.
Su'ud, Z., Ilham, M., Widiawati, N., & Sekimoto, H. (2018). Modified CANDLE Burnup Calculation System, Its Evolution, and Future Development. J. Phys.: Conf. Ser. 1090 012006.
Su’ud, Z., & Sekimoto, H. (2013). The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input. Annals of Nuclear Energy, 54, 58-66.
Zweifel, P.F. (1973). Reactor Physics. McGraw-Hill : USA.
DOI: http://dx.doi.org/10.20527/flux.v1i1.7184
Article Metrics
Abstract view : 724 timesPDF (Bahasa Indonesia) - 545 times
Refbacks
- There are currently no refbacks.
Copyright (c) 2020 Jurnal Fisika Flux: Jurnal Ilmiah Fisika FMIPA Universitas Lambung Mangkurat

This work is licensed under a Creative Commons Attribution 4.0 International License.
Association with:
Indexed by:

Jurnal Fisika FLux: Jurnal Ilmiah FMIPA Universitas Lambung Mangkurat is licensed under a Creative Commons Attribution-NoDerivatives 4.0 International License.










