Evaluating the JEFF 3.1, ENDF/B‑VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel  

作　　者：Cici Wulandari Abdul Waris Sidik Permana Syeilendra Pramuditya 

机构地区：[1]Department of Physics,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Bandung 40132,Indonesia [2]Nuclear Physics and Biophysics Research Division,Department of Physics,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Bandung 40132,Indonesia [3]Department of Nuclear Science and Engineering,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Jl.Ganesa 10,Bandung 40132,Indonesia

出　　处：《Nuclear Science and Techniques》2022年第12期173-189,共17页核技术（英文）

摘　　要：This study evaluated the nuclear data libraries for a small 100 Mega Watt electric(MWe)Molten Salt Reactor with plutonium fuel.The reactor has a power output of 100 MWe,which meets the demand for electricity generation in several regions or provinces outside Java Island.Several nuclear data libraries,such as JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,were used for a more comprehensive evaluation.LiF–BeF_(2)–ThF_(4)–PuF_(4) was used as the initial fuel composition.The thorium and plutonium concentrations in the fuel salt were varied to obtain the optimum fuel composition,leading to critical conditions.The results showed some neutronic parameters,such as the conversion ratio,neutron spectra,and effective multiplication factors,from three different nuclear data libraries.By changing the plutonium concentration in the initial fuel salt composition,the minimum plutonium loaded for the reactor criticality during 2000 days of operation time was determined to be 0.995,0.91,0.87,and 0.90 mol%for JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,respectively.The differences in the values of each parameter were due to several factors,such as the cross-section values and number of nuclides in the nuclear data libraries.Several safety parameters were also investigated to ensure the possibility of utilizing PuF_(4) in the reactor.

关 键 词：NEUTRONICS PLUTONIUM Small MSR THORIUM SRAC 

分 类 号：TM623[电气工程—电力系统及自动化]