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Abstract
Analysis of the criticality and conversion ratio of a gas-cooled fast reactor (GFR) with various UN-PuN fuel fractions using modified CANDLE scheme burn-up in radial direction has been conducted. The fuel fraction varies from 40% - 60% with 5% intervals, the cladding fraction is 10% and the coolant fraction varies from 30% -50%. Data calculations were performed using SRAC 2006 programming with JENDL 4.0 library data. The reactor is divided into 10 regions with equal volume in the radial direction. Each region is filled with natural uranium fuel without enrichment with different burn-up levels. Regions are arranged in such a way that the reactor can reach critical conditions throughout the burn-up period. The results showed that variations in the 40% fuel fraction had not been able to reach critical conditions at the beginning of life, while 45%-60% fuel fraction variations had reached reactor criticality. The conversion ratio for all fuel fractions is greater than 1, which indicates that a breeding process appears in the GFR reactor core. The conversion ratio for all variations in fuel fractions has almost the same pattern for all regions. The first region has the largest conversion ratio value because it has natural uranium as fuel input which has the highest density compared to other regions.
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Copyright (c) 2023 Feriska Handayani Irka, Zaki Su'ud, Dwi Irwanto, Siti Nurul Khotimah, Hiroshi Sekimoto

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References
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References
Pioro I. L, Handbook of Generation IV Nuclear Reactors Worehead Publishing Series in Energy 103 1-10, 2016.
World nuclear association, Uranium Enrichment, 2022.
Batan, Prinsip Reaktor Pembiak Cepat, Ensiklopedi, 2023.
Murray, L. Raymond dan Holbert, Keith E. Nuclear Energy (eighth edition), book chapter science direct, 505-523, 2020.
Feinberg, S. M. Discussion Comment, Rec. Of Proc. Session B-10. ICPUAE, United Nations, Geneva, Switzerland, 1958.
Zhang, D., Chen, X. N., Flad, M., Rineiski, A. & Maschek, W. Theoretical and numerical studies of TWR based on ESFR core design. Energy Convers. Manag., 72, 12–18, 2013.
Zhang, D. et al. Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor. Sci. China Technol. Sci. 57, 1229–1237, 2014.
Sekimoto, H., Ryu, K. & Yoshimura, Y. CANDLE: The new burn-up strategy. Nucl. Sci. Eng. 139, 306–317, 2001.
Su’ud, Z. & Sekimoto, H. Optimization of Modified Candle Burn-up Scheme Based Long Life Pb-Bi Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input, Japan: N. P., 2008.
Su’ud, Z. & Sekimoto, H. The prospect of gas-cooled fast reactors for long-life reactors with natural uranium as fuel cycle input. Ann. Nucl. Energy 54, 58–66, 2013.
Rida, S. N. M. & Su’ud, Z. A design study of Pb-Bi-cooled fast reactors with natural uranium as the fuel cycle input. Int. J. Nucl. Energy Sci. Technol. 4, 217–222, 2009.
Su’ud, Z., Ilham, M., Widiawati, N. & Sekimoto, H. Modified CANDLE Burn-up Calculation System, Its Evolution, and Future Development. J. Phys. Conf. Ser. 1090, 2018.
Su’ud, Z., Irka, F. H., Imam, T. T., Sekimoto, H. & Sidik, P. Desain study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special shuffling strategy in radial direction. Advance Material Research, 772, 530–535 ,2013.
Duderstadt, J. J. dan Hamilton, L. J. Nuclear Reactor Analysis, John Wiley Sons, 1976.
Rouault, J. dan Wei, T.Y.C., The Gen IV Gas Cooled Fast Reactor: Statues of Studies, nuclear energy agency,2005.
Okumura, K., T. Kugo, K. Kaneko, dan K. Tsuchihashi, SRAC2006: A Comprehensive Neutronics Calculation Code System, Japan: Japan Atomic Energy Agency, 2007.
K. Shibata, O. Iwamoto, T. Nakagawa et al., JENDL-4.0: a new library for nuclear science and engineering, J. Nucl. Sci. Technol., 48, 1–30, 2011.