Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nuclear data library  

作　　者：Fatima IAl-Hamadi Bassam AKhuwaileh Peng Hong Liem Donny Hartanto 

机构地区：[1]Department of Mechanical and Nuclear Engineering,University of Sharjah,P.O.BOX 27272,Sharjah,United Arab Emirates [2]Graduate School of Engineering,Cooperative Major in Nuclear Energy,Tokyo City University(TCU),1-28-1 Tamazutsumi,Setagaya,Tokyo,Japan [3]Scientific Computational Division,Nippon Advanced Information Service(NAIS Co.,Inc.),416 Muramatsu,Tokaimura,Ibaraki,Japan

出　　处：《Nuclear Science and Techniques》2020年第12期77-87,共11页核技术（英文）

基　　金：the Research Institute of Science and Engineering at the University of Sharjah(No.1802040790-P).

摘　　要：This study presents a benchmark evaluation of the new ENDF/B-VIII.0 nuclear data library for the Organization for Economic Co-operation and Development/Nuclear Energy Agency Medium 1000 MWth sodium-cooled fast reactor(SFR).The study presented herein covers both SFR core types,i.e.,metallic fueled(MET-1000)and oxide fueled(MOX-1000),simulated using the continuous-energy Monte Carlo Serpent2 code.The neutronics performances of the ENDF/B-VIII.0-based simulations were compared mainly to two libraries:ENDF/B-VII.1 and JENDL-4.0.The comparison includes several neutronics parameters evaluated for the beginning and end of the cycle conditions.These parameters include the effective multiplication factor keff,total effective delayed neutron fraction beff,sodium void reactivity(DqNa),Doppler constant(DqDoppler),and control rod worth(DqCR).In addition,a sensitivity study was used to reveal the major isotope/reaction pairs contributing to the discrepancy observed in the performance of the three libraries using 33 and 44-energy-group structures.

关 键 词：Serpent ENDF/B-VIII.0 Sodium-cooled fast reactor Sensitivity analysis 

分 类 号：TL433[核科学技术—核技术及应用]