基于非结构网格输运模型的核-热耦合程序的开发与验证  

Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model

作　　者：杨鸣睿 孙启政 罗池旭 何东豪 刘晓晶[1] 张滕飞 YANG Mingrui;SUN Qizheng;LUO Chixu;HE Donghao;LIU Xiaojing;ZHANG Tengfei(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China)

机构地区：[1]上海交通大学、核科学与工程学院,上海200240

出　　处：《核技术》2023年第3期76-86,共11页Nuclear Techniques

基　　金：国家自然科学基金(No.12175138);中核集团"青年英才"科研项目资助。

摘　　要：反应堆内存在着中子物理、流动传热等多种物理场的紧密耦合和相互反馈。为了能准确地模拟反应堆内的真实情况,本研究针对先进复杂反应堆开发了非结构网格核-热耦合程序MORPHY。中子物理求解采用三角形变分节块法方法结合刚性限制法求解时空中子输运方程;热工水力求解基于一维的并联通道模型和圆柱导热模型。采用TWIGL基准题验证了中子动力学的准确性,堆芯相对功率与参考结果的偏差小于0.5%。与Dodds基准题结果对比,验证了程序对于非结构网格的描述能力。基于NEACRP压水堆基准题对程序的核热耦合计算能力进行验证,并分析对比了不同耦合方法、角度离散阶数对结果的影响。结果表明:MORPHY程序计算值与TWIGL、Dodds以及NEACRP基准题参考值吻合良好,能够用于堆芯稳态和瞬态核热耦合分析模拟。[Background]There is usually a strong coupling of neutronics-thermal hydraulics(N-TH)fields inside nuclear reactors.[Purpose]This study aims to accurately simulate the multi-physics fields in nuclear reactors by developing a three-dimensional N-TH coupling code MORPHY tailored to advanced complex reactors.[Methods]First of all,a three-dimensional triangular-z nodal variational nodal method(VNM)was employed for neutronics calculation.and the stiffness confinement method(SCM)was used to solve the neutron temporal-spatial equation;thermal hydraulic calculations were based on the one-dimensional multi-channel model and the one-dimensional cylindrical thermal conductivity model.Then,the accuracy of neutron dynamics was verified by TWIGL benchmark,Dodds benchmark,and the typical pressurized water reactor(PWR)benchmark NEACRP.Finally,the effects of different coupling methods and angle discrete orders on the results were analyzed and compared against reference solutions by PARCS.[Results]Verification results of TWIGL benchmark show that the deviation of relative power from the reference results is less than 0.5%.Compared with the results of Dodds benchmark,it verifies the MORPHY code's ability to describe unstructured meshes.The transient coupling calculation capability of MORPHY is verified by NEACRP benchmark.[Conclusions]Numerical solutions by MORPHY are in good agreement with reference results of the TWIGL,Dodds and NEACRP benchmark problems.It is concluded that MORPHY can adapt to the transient N-TH coupling analysis of nuclear reactor cores.

关 键 词：中子动力学 刚性限制法 核热耦合计算 瞬态 输运程序 

分 类 号：TL327[核科学技术—核技术及应用]