CAJ | 학술논문

针对超临界水堆堆芯内流体物性分布非均匀性显著、核热反馈强烈的特点,建立了适用于超临界水堆运行环境的、基于燃料棒层面的精细化堆芯中子学/热工水力耦合方法,开发了子通道程序 NCED-SCWR、节块扩散计算程序 MRAPS、多功能程序 COUPLE,结合西屋公司组件能谱计算程序PARAGON,构建了堆芯中子学/热工耦合分析程序系统 SCAP.以具有121盒燃料组件的超临界水堆堆芯进行模拟分析,研究了堆芯三维功率分布和流体物性分布的特点以及反应性参数与重要同位素密度等随燃耗的变化规律.结果表明,本文提出的精细化核热耦合方法和开发的程序系统可以应用于超临界水堆堆芯的研究与分析,相关研究结果对超临界水堆堆芯设计具有一定的指导意义.
침대초림계수퇴퇴심내류체물성분포비균균성현저、핵열반궤강렬적특점,건립료괄용우초림계수퇴운행배경적、기우연료봉층면적정세화퇴심중자학/열공수력우합방법,개발료자통도정서 NCED-SCWR、절괴확산계산정서 MRAPS、다공능정서 COUPLE,결합서옥공사조건능보계산정서PARAGON,구건료퇴심중자학/열공우합분석정서계통 SCAP.이구유121합연료조건적초림계수퇴퇴심진행모의분석,연구료퇴심삼유공솔분포화류체물성분포적특점이급반응성삼수여중요동위소밀도등수연모적변화규률.결과표명,본문제출적정세화핵열우합방법화개발적정서계통가이응용우초림계수퇴퇴심적연구여분석,상관연구결과대초림계수퇴퇴심설계구유일정적지도의의.
According to the intense flow heterogeneity and strong neutronics/thermal-hydraulic feedback of SCWR,a pin-wise neutronics and thermal-hydraulic coupling method is developed and a core analysis code package SCAP is established.The package utilizes sub-channel program NCED-SCWR,lattice program PARAGON, nodal diffusion program MRAPS, and multi-functional code COUPLE.Furthermore, 3D core power distribution and flow distribution, reactivity parameters and isotope density are studied for a typical core with 121 fuel assemblies.The results show that both the coupling method and code package are applicable to the SCWR core analysis.The obtained conclusion will be benefit for SCWR core design.