Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code

Authors

  • Ratna Dewi Syarifah Universitas Jember
  • Nabil Nabhan MH
  • Zein Hanifah
  • Iklimatul Karomah
  • Ahmad Muzaki Mabruri
  • Artoto Arkundato

DOI:

https://doi.org/10.31599/jaring-saintek.v3i1.333

Keywords:

GFR, uranium carbide, SRAC Code, JENDL 4.0

Abstract

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.

Downloads

Download data is not yet available.

References

[1] GIF. (2014). Generation IV International Forum Research Technology Roadmap Update for Generation IV Nuclear Energy System. GIV-IV (The Generation IV International Forum) and the OECD Nuclear Energy Agency

[2] 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

[3] Anzieu (2009) Anzieu, P., Stainsby, R. dan Mikityuk, K (2009): Gas Cooled Fast Reactor (GFR) Overview and Perspective, GIF Symposium, Paris, France, 127-134

[4] 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

[5] 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

[6] 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

[7] 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

[8] 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

[9] 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

[10] 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

[11] 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

[12] 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

[13] Okumura, K., (2002): SRAC2002: The comprehensive Neutronic Calculation Code System. Japan Atomic Energy Agency (JAEA), Japan

Downloads

Published

2021-04-28

Issue

Vol. 3 No. 1 (2021): April 2021

Section

Artikel