Article: A comparison of neutronic studies on 400 MW thermal fast reactor with modified CANDLE burn-up schemes using helium gas, lead bismuth eutectic and liquid sodium coolants Journal: International Journal of Nuclear Energy Science and Technology (IJNEST) 2024 Vol.17 No.1 pp.66 - 84 Abstract: One of the most essential technical challenges in fast reactor design is coolant selection. This paper investigates neutronic studies on a 400 MW thermal Modified CANDLE burnup scheme in a fast reactor using helium gas, lead-bismuth eutectic, and liquid sodium coolants. The core has been separated into ten regions with the equivalent volume in radial direction and recharging every ten years. Natural uranium was loaded in the first region, and after ten years, it was transported to the second region. These movements have taken place in all regions and fuel in tenth region got out of core. The neutronic features such as burnup level, integral conversion ratio, relative power density, flux level, infinite multiplication factor and effective multiplication factor were carried out. According to the results of the multiplication factor, liquid sodium attained criticality faster than helium gas and lead-bismuth eutectic coolants. This makes it to be the best coolant. Inderscience Publishers - linking academia, business and industry through research

Title: A comparison of neutronic studies on 400 MW thermal fast reactor with modified CANDLE burn-up schemes using helium gas, lead bismuth eutectic and liquid sodium coolants

Authors: Jean Pierre Ndayiragije; Zaki Su'ud; Abdul Waris

Addresses: Nuclear Physics and Biophysics Research Group, Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia ' Nuclear Physics and Biophysics Research Group, Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia ' Nuclear Physics and Biophysics Research Group, Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia

Abstract: One of the most essential technical challenges in fast reactor design is coolant selection. This paper investigates neutronic studies on a 400 MW thermal Modified CANDLE burnup scheme in a fast reactor using helium gas, lead-bismuth eutectic, and liquid sodium coolants. The core has been separated into ten regions with the equivalent volume in radial direction and recharging every ten years. Natural uranium was loaded in the first region, and after ten years, it was transported to the second region. These movements have taken place in all regions and fuel in tenth region got out of core. The neutronic features such as burnup level, integral conversion ratio, relative power density, flux level, infinite multiplication factor and effective multiplication factor were carried out. According to the results of the multiplication factor, liquid sodium attained criticality faster than helium gas and lead-bismuth eutectic coolants. This makes it to be the best coolant.

Keywords: fast reactor; coolant; modified CANDLE; SRAC; JENDL 4.0; effective multiplication factor.

DOI: 10.1504/IJNEST.2024.139137

International Journal of Nuclear Energy Science and Technology, 2024 Vol.17 No.1, pp.66 - 84

Received: 03 Nov 2023
Accepted: 07 Mar 2024
Published online: 14 Jun 2024 *

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Title: A comparison of neutronic studies on 400 MW thermal fast reactor with modified CANDLE burn-up schemes using helium gas, lead bismuth eutectic and liquid sodium coolants

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