Core designing of a new type of TVS-2M FAs:neutronics and thermal-hydraulics design basis limits

作     者：Saeed GHAEMI Farshad FAGHIHI Saeed GHAEMI;Farshad FAGHIHI

作者机构：Department of Nuclear EngineeringSchool of Mechanical EngineeringShiraz UniversityShiraz 71936-16548Iran Radiation Research CenterShiraz UniversityShiraz 71936Iran Lonizing and Non-Ionizing Radiation CenterShiraz University of Medical ScienceShirazIran 

出 版 物：《Frontiers in Energy》 (能源前沿（英文版）)

年 卷 期：2021年第15卷第1期

页      面：256-278页

核心收录：

学科分类：0808[工学-电气工程] 07[理学] 0807[工学-动力工程及工程热物理] 070202[理学-粒子物理与原子核物理] 0702[理学-物理学] 

基　　金：Sincere thanks are due to the Shiraz University Research Council for his financial support 

主　　题：TVS-2M FAs core design basis limits VVER-1000 analysis mixture of uranium-gadolinium oxides fuels thermal-hydraulics PARCS WIMS-D5 

摘      要：One of the most important aims of this study is to improve the core of the current VVER reactors to achieve more burn-up(or more cycle length)and more intrinsic *** is an independent study on the Russian new proposed FAs,called TVS-2M,which would be applied for the future advanced *** important aspects of neutronics as well as thermal hydraulics investigations(and analysis)of the new type of Fas are conducted,and results are compared with the standards PWR *** TVS-2M FA contains gadolinium-oxide which is mixed with UO_(2)(for different Gd densities and U-235 enrichments which are given herein),but the core does not contain *** new type TVS-2M Fas are modeled by the SARCS software package to find the PMAXS format for three states of CZP and HZP as well as HFP,and then the whole core is simulated by the PARCS code to investigate transient *** addition,the WIMS-D5 code is suggested for steady core modeling including TVS-2M FAs and/or TVS *** neutronics aspects such as the first cycle length(first cycle burn up in terms of MWthd/kgU),the critical concentration of boric acid at the BOC as well as the cycle length,the axial,and radial power peaking factors,differential and integral worthy of the most reactive CPS-CRs,reactivity coefficients of the fuel,moderator,boric acid,and the under-moderation estimation of the core are conducted and benchmarked with the PWR ***,the burn-up calculations indicate that the 45.6 d increase of the first cycle length(which corresponds to 1.18 MWthd/kgU increase of burnup)is the best improving aim of the new FA type called ***,thermal-hydraulics core design criteria such as MDNBR(based on W3 correlation)and the maximum of fuel and clad temperatures(radially and axially),are investigated,and discussed based on the CDBL.