Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code
Analysis of fuel volume fraction with uranium caride fuel in Gas Cooled Fast Reactor (GFR) with SRAC Code is has been done. The calculation used SRAC Code (Standard Reactor Analysis Code) which is developed by JAEA (Japan Atomic Energy Agency), and the data libraries nuclear used JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. From the analysis of fuel volume fraction, when the volume fraction is increase, the k-eff value is increase. And the optimum design after has been analysis for fuel volume fraction, that is the fuel volume fraction is 49% with a heterogeneous core configuration of three types of fuel percentages, for Fuel1 9%, Fuel2 12% and Fuel3 15%. This reactor is cylindrical, has a core diameter of 240 cm and a core height of 100 cm.
 GIF. (2002) A technology Roadmap for Generation IV Nuclear Energy System. GIF-IV (The Generation IV International Forum) and U.S DOE Nuclear Energy Research Advisory Committee
 Anzieu (2009) Anzieu, P., Stainsby, R. dan Mikityuk, K (2009): Gas Cooled Fast Reactor (GFR) Overview and Perspective, GIF Symposium, Paris, France, 127-134
 Syarifah, R. D., Yulianto Y., Su’ud Z., Basar K, & Irwanto D. (2016). Neutronic Analysis of Thorium Nitride (Th, U233)N Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Long life without Refueling, Key Engineering Materials, ISSN: 1662-9795, Vol. 733, pp 47-50, doi:10.4028/www.scientific.net/KEM.733.47
 Syarifah, R. D., Su’ud Z., Basar K, & Irwanto D. (2016). Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling, MATEC Web of Conferences, 2016, 82, 03008, DOI: 10.1051/matecconf/20168203008
 Syarifah, R. D., Su’ud Z., Basar K, & Irwanto D. (2016). The Prospect of Uranium Nitride (UN-PuN) Fuel for 25-100MWe Gas Cooled Fast Reactor Long Life without Refuelling. Journal of Physics: Conference Series 776 (2016) 012103, DOI:10.1088/1742-6596/776/ 1/012103
 Syarifah, R. D., Su’ud Z., Basar K, Irwanto D., Pattipawaej S. C. & Ilham M. (2017). Comparison of Uranium and Thorium Nitride Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Longlife without Refueling, International Journal of Energy Research, Special Issue Paper, page 1-7, doi:10.1002/er.3923
 Syarifah, R. D., Su’ud Z., Basar K, & Irwanto D. (2017). Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling, IOP Conf. Series: Journal of Physics: Conf. Series 799 (2017) 012022, doi:10.1088/1742-6596/799/1/012022
 Syarifah, R. D., Su’ud Z., Basar, K, & Irwanto, D. (2017). Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling. IOP Conf. Series: Journal of Physics: Conf. Series 1090 (2018) 012033, doi :10.1088/1742-6596/1090/ 1/012033
 Fareha, M.A., Syarifah, R. D., Su’ud Z & Kurniasih N. (2018). Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors. IOP Conf. Series: Journal of Physics: Conf. Series 1090 (2018) 012021. doi :10.1088/1742-6596/1090/ 1/012021
 Syarifah, R. D., Su’ud Z., Basar, K, & Irwanto, D. (2020). Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor. Journal of Physics: Conference Series 1493 (2020) 012020. doi:10.1088/1742-6596/1493/1/012020
 Syarifah, R. D., Arkundato, A., Su’ud Z. & Irwanto, D. (2020). Neutronic analysis of comparation UN-PuN fuel and ThN fuel for 300MWth Gas Cooled Fast Reactor long life without refueling. IOP Conf. Series: Journal of Physics: Conf. Series 1436 (2020) 012132, doi:10.1088/1742-6596/1436/1/012132
 Okumura, K., (2002): SRAC2002: The comprehensive Neutronic Calculation Code System. Japan Atomic Energy Agency (JAEA), Japan
Copyright (c) 2021 Jurnal Jaring SainTek
This work is licensed under a Creative Commons Attribution 4.0 International License.