典型文献
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
文献摘要：
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-BeF2-ThF4-PuF4 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 criti-cal 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 PuF4 in the reactor.
文献关键词：
中图分类号：
作者姓名：
Cici Wulandari;Abdul Waris;Sidik Permana;Syeilendra Pramuditya
作者机构：
Department of Physics,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Bandung 40132,Indonesia;Nuclear Physics and Biophysics Research Division,Department of Physics,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Bandung 40132,Indonesia;Department of Nuclear Science and Engineering,Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,Jl.Ganesa 10,Bandung 40132,Indonesia
文献出处：
引用格式：
[1]Cici Wulandari;Abdul Waris;Sidik Permana;Syeilendra Pramuditya-.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)[J].核技术（英文版）,2022(12):173-189
A类：
ThF4,PuF4,neutronic
B类：
Evaluating,JEFF,ENDF,JENDL,nuclear,data,libraries,small,MWe,molten,salt,reactor,plutonium,fuel,This,study,evaluated,Mega,Watt,Molten,Salt,Reactor,has,power,output,which,meets,demand,electricity,generation,several,regions,provinces,outside,Java,Island,Several,such,were,used,more,comprehensive,evaluation,LiF,BeF2,was,initial,composition,thorium,concentrations,varied,obtain,optimum,leading,conditions,results,showed,some,parameters,conversion,spectra,effective,multiplication,factors,from,three,different,By,changing,minimum,loaded,criticality,during,days,operation,determined,respectively,differences,values,each,due,cross,section,number,nuclides,safety,also,investigated,ensure,possibility,utilizing
AB值：
0.468061
相似文献
机标中图分类号，由域田数据科技根据网络公开资料自动分析生成，仅供学习研究参考。
