Study on Utilization of Super Grade Plutonium in Molten Salt Reactor FUJI-U3 using CITATION Code

International Conference on Energy Sciences 2016

能源学;物理学

Wulandari, Cici^1 ; Waris, Abdul^1 ; Pramuditya, Syeilendra^1 ; Asril, Pramutadi A.M.^1 ; Novitrian^1

Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10, Bandung

40132, Indonesia^1

关键词: As substitutions;    Chemical compositions;    Core region;    Fissile materials;    JENDL3.2;    Neutronics;    Nuclear data library;    Super-grade;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/877/1/012021/pdf
DOI  :  10.1088/1742-6596/877/1/012021

来源: IOP

【 摘 要 】

FUJI-U3 type of Molten Salt Reactor (MSR) has a unique design since it consists of three core regions in order to avoid the replacement of graphite as moderator. MSR uses floride as a nuclear fuel salt with the most popular chemical composition is LiF-BeF2-ThF4-233UF4. ThF4and233UF4are the fertile and fissile materials, respectively. On the other hand, LiF and BeF2working as both fuel and heat transfer medium. In this study, the super grade plutonium will be utilized as substitution of233U since plutonium is easier to be obtained compared to233U as main fuel. Neutronics calculation was performed by using PIJ and CITATION modules of SRAC 2002 code with JENDL 3.2 as nuclear data library.