Study on Coupling of NLSANMT and RELAP5/mod3.2
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摘要: 在系统热工水力程序RELAP5/mod3.2的基础上,采用显式方法建立了堆芯三维时空中子动力学与一维热工水力计算的耦合模型,接入基于非线性迭代半解析节块法的三维瞬态物理分析模型(NLSANMT)后,形成了一个具有堆芯三维瞬态物理特性分析能力的系统计算程序NLSANMT/RELAP5(mod3.2)。通过核动力反应堆温度反馈系数、堆芯功率分布参数的校算及单束控制棒失控抽出事故的模拟分析,验证了接口的正确性。验证结果表明,与RELAP5/mod3.2相比,所开发的NLSANMT/RELAP5(mod3.2)程序具有更强的堆芯物理瞬态分析能力。Abstract: Based on the thermal-hydraulic code RELAP5/mod3.2,the coupling model of three-dimension space-time neutron kinetics and one-dimension thermal-hydraulic computation is established by the explicit method,and the three-dimension transient physical analysis model based on the show that the developed NLSANMT/RELAP5（mod3.2） program system is with better ability for core transient analysis,compared with RELAP5/mod3.2.nonlinear iterative Semi-Analytical Nodal code NLSANMT is transplanted.Proof-checking and computation of feedback coefficients and steady parameters of nuclear power reactor,and the simulation analysis of the uncontrolled accidental draw-out of one bundle of control rods prove the validity of the interface.The results show that the developed NLSANMT/RELAP5(mod3.2) program system is with better ability for core transient analysis, compared with RELAP5/mod3.2.
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