原子能科学技术2016，Vol.50Issue(6)：1047-1053,7.DOI:10.7538/yzk.2016.50.06.1047
超临界水冷堆环形燃料组件核热耦合分析
Coupled Neutronics and Thermal-hydraulics Analysis of Annular Fuel Assembly for SCWR
摘要
Abstract
During the pre-conceptual design of supercritical water-cooled reactor (SCWR),assembly design is very important and affects core performance.Coupled neutronics and thermal-hydraulics analysis is required for dramatic changes of water density in SCWR.Annular fuel assembly was optimized from the point of view of neutronics and thermal-hydraulics performance using three-dimensional coupling code.Three-dimensional diffusion calculation for annular fuel assemblies was carried out using FENNEL-N and pin power distributions were obtained.With these pin power distributions,SUBSC was used to perform the sub-channel analysis.The effects of fuel rod distance and gap between fuel rods and assembly box on assembly performance were researched in the coupled analysis.Results show that increasing fuel rod distance and rod-to-box gap will increase kinf and assembly power peaking factor.It is also shown in the results that heating heterogeneity of sub-channels plays a big role in assembly thermal performance and adding grid will flatten coolant outlet temperature as well as decrease maximum cladding surface temperature.Safety analysis of annular fuel assembly shows that the assembly is safe from the point of view of neutronics.关键词
环形燃料/超临界水冷堆/核热耦合Key words
annular fuel/supercritical water-cooled reactor/coupled neutronics and thermal-hydraulics分类
能源科技引用本文复制引用
赵传奇,王昆鹏,曹良志,吴宏春,郑友琦..超临界水冷堆环形燃料组件核热耦合分析[J].原子能科学技术,2016,50(6):1047-1053,7.基金项目
国家自然科学基金资助项目(91226106) （91226106）
