堆芯上腔三维化的池式快堆系统分析软件开发
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摘要
针对目前我国快堆系统分析软件主要采用国外引进方式而导致难以掌握核心物理模型的现状,本文首先通过开发中子动力学模型、堆芯及其热钠池模型、中间热交换器模型、一回路和中间回路热量传输系统模型、三回路模型等,自主开发出基于Compaq Visual Fortran的适用于稳态计算的池式快堆系统分析软件SAC-CFR (System Analysis Code for Pool-type Fast Reactor in China)。在此基础上,通过进一步开发系统部件的瞬态模型、控制系统和保护系统模型,及确定瞬态工况热工水力学的求解逻辑和稳定性标准,完成SAC-CFR瞬态计算功能的开发。
堆芯上腔三维化的池式快堆系统分析软件SAC-CFR具有以下特点：中子动力学模型采用传统的、计算方法较为成熟的点堆模型,并且采用瞬跳近似和分段多项式逼近两种方法求解点堆方程。热钠池模型为基于直角坐标系和柱坐标系下的三维计算模型,具有一定的先进性。应用多孔介质方法建立钠池内中间热交换器、主泵、事故热交换器及屏蔽柱模型,完成了含有多孔介质模型和复杂几何边界的钠池三维计算模型开发,并完成了该三维模型向SAC-CFR的嵌入。
应用SAC-CFR对中国实验快堆三个回路系统建模,分析其在不同功率台阶稳态运行时系统的热工水力学状态,验证了所开发稳态模型的计算精度。之后,应用SAC-CFR对文殊快堆45%功率汽机跳闸工况进行建模分析,将计算所得的一回路流量、主容器进出口温度、中间热交换器出口温度等关键参数与堆内实测数据进行对比,发现各参数变化趋势一致,初步验证了该软件用于系统瞬态分析的有效性。
最后,应用堆芯上腔三维化的SAC-CFR分析文殊堆停堆瞬态过程中上腔室内热工水力学特性,发现了文殊堆上腔室内流体热分层特点；分析中国实验快堆在稳态运行和紧急停堆工况下钠池内的流场分布,验证多孔介质模型的合理性,得到了钠池内流场分布特点。
作为系统软件SAC-CFR开发工作的延伸,通过建立非能动余热排出系统(Passive Direct Reactor Auxiliary Cooling Syste, PDRACS)内事故热交换器、空冷器、一回路和中间回路管道内的热工水力学模型,开发出非能动余热排出系统的计算程序。稳态初始化之后,用该程序模拟反应堆跳闸的同时空冷器风门打开的瞬态工况,得到了中间回路自然循环的流量、PDRACS带走的功率、空冷器出口空气温度、中间热交换器两侧温度等参数随时间的变化。
Aiming at developing system analysis code independently, a System Analysis Code for Pool-type Fast Reactor in China (SAC-CFR), with neutron kinetics model, core and hot pool model, intermediate heat exchanger model, primary and intermediate heat transport system, steam generation system, was developed based on Compaq Visual Fortran to analyze the thermal-hydraulic characteristic of fast reactor under steady state operation. Then the transient calculation function of SAC-CFR was developed with further development of component transient model, plant control and protection system model, transient calculation logic and stability criteria.
The newly developed SAC-CFR is characterized by three aspects. Firstly, the conventional point reactor neutron kinetics model was chosen to calculate the time dependent fission power with prompt jump approximation (PJA) method and piecewise polynomial approximation method. Secondly, the hot pool was analyzed with three-dimensional model developed based on SIMPLE algorithm on stagger grid under Cartesian coordinates and cylindrical coordinates. Thirdly, The three-dimensional hot pool analysis model was updated after incorporating porous medium model of penetration components and complex geometry component. Penetration components included intermediate heat exchanger (IHX), primary pump, decay heat exchanger (DHX), and radial shielding. Then the updated three-dimensional model was embedded into SAC-CFR.
Then the newly developed code was used to analyze system thermal-hydraulic characteristic of China Experimental Fast Reactor (CEFR) under steady state operation of different power level. The good agreements between the simulation results and data in CEFR safety analysis report (SAR) showed that the present model is effective. The transient started from turbine trip test at45%thermal output in the Monju plant was analyzed with SAC-CFR. The simulation results, such as mass flow rate in primary loop, coolant temperature at inlet and outlet of main vessel, coolant temperature at outlet of intermediate heat exchanger (IHX), were compared with the data tested in reactor. A good agreement between the calculated results and the test data was obtained.
Finally, the system analysis code with three-dimensional hot pool model was used to analyze the thermal-hydraulic behavior in upper plenum of "MONJU" FBR during reactor scram transient, and the flow field in CEFR hot pool under steady-state operation condition and after scram. Some thermal stratification characteristics in Monju was founded. The agreement between the computational flow field and hot pool geometry of CEFR showed the effectiveness of porous medium model. Also, some characteristic of flow field was founded.
As the extension of SAC-CFR development, an analysis code to perform thermal-hydraulic calculation in Passive Direct Reactor Auxiliary Cooling System (PDRACS) was developed through the coupling of thermal-hydraulic response in direct heat exchanger (DHX), air heat exchanger (AHX) and circuits of PDRACS. After steady-state initialization, a transient starting from air damper opening at the instant of reactor scram was simulated. Key parameters, such as mass flow rate in intermediate loop under natural circulation, heat removed by PDRACS, air temperature at AHX outlet, coolant temperature at both side of DHX, are calculated, which preliminary showed the effectiveness of the code. And the newly developed code is now ready to be incorporated into SAC-CFR to perform the interactive response between the PDRACS and the whole system after scram.
堆芯上腔三维化的池式快堆系统分析软件SAC-CFR具有以下特点：中子动力学模型采用传统的、计算方法较为成熟的点堆模型,并且采用瞬跳近似和分段多项式逼近两种方法求解点堆方程。热钠池模型为基于直角坐标系和柱坐标系下的三维计算模型,具有一定的先进性。应用多孔介质方法建立钠池内中间热交换器、主泵、事故热交换器及屏蔽柱模型,完成了含有多孔介质模型和复杂几何边界的钠池三维计算模型开发,并完成了该三维模型向SAC-CFR的嵌入。
应用SAC-CFR对中国实验快堆三个回路系统建模,分析其在不同功率台阶稳态运行时系统的热工水力学状态,验证了所开发稳态模型的计算精度。之后,应用SAC-CFR对文殊快堆45%功率汽机跳闸工况进行建模分析,将计算所得的一回路流量、主容器进出口温度、中间热交换器出口温度等关键参数与堆内实测数据进行对比,发现各参数变化趋势一致,初步验证了该软件用于系统瞬态分析的有效性。
最后,应用堆芯上腔三维化的SAC-CFR分析文殊堆停堆瞬态过程中上腔室内热工水力学特性,发现了文殊堆上腔室内流体热分层特点；分析中国实验快堆在稳态运行和紧急停堆工况下钠池内的流场分布,验证多孔介质模型的合理性,得到了钠池内流场分布特点。
作为系统软件SAC-CFR开发工作的延伸,通过建立非能动余热排出系统(Passive Direct Reactor Auxiliary Cooling Syste, PDRACS)内事故热交换器、空冷器、一回路和中间回路管道内的热工水力学模型,开发出非能动余热排出系统的计算程序。稳态初始化之后,用该程序模拟反应堆跳闸的同时空冷器风门打开的瞬态工况,得到了中间回路自然循环的流量、PDRACS带走的功率、空冷器出口空气温度、中间热交换器两侧温度等参数随时间的变化。
Aiming at developing system analysis code independently, a System Analysis Code for Pool-type Fast Reactor in China (SAC-CFR), with neutron kinetics model, core and hot pool model, intermediate heat exchanger model, primary and intermediate heat transport system, steam generation system, was developed based on Compaq Visual Fortran to analyze the thermal-hydraulic characteristic of fast reactor under steady state operation. Then the transient calculation function of SAC-CFR was developed with further development of component transient model, plant control and protection system model, transient calculation logic and stability criteria.
The newly developed SAC-CFR is characterized by three aspects. Firstly, the conventional point reactor neutron kinetics model was chosen to calculate the time dependent fission power with prompt jump approximation (PJA) method and piecewise polynomial approximation method. Secondly, the hot pool was analyzed with three-dimensional model developed based on SIMPLE algorithm on stagger grid under Cartesian coordinates and cylindrical coordinates. Thirdly, The three-dimensional hot pool analysis model was updated after incorporating porous medium model of penetration components and complex geometry component. Penetration components included intermediate heat exchanger (IHX), primary pump, decay heat exchanger (DHX), and radial shielding. Then the updated three-dimensional model was embedded into SAC-CFR.
Then the newly developed code was used to analyze system thermal-hydraulic characteristic of China Experimental Fast Reactor (CEFR) under steady state operation of different power level. The good agreements between the simulation results and data in CEFR safety analysis report (SAR) showed that the present model is effective. The transient started from turbine trip test at45%thermal output in the Monju plant was analyzed with SAC-CFR. The simulation results, such as mass flow rate in primary loop, coolant temperature at inlet and outlet of main vessel, coolant temperature at outlet of intermediate heat exchanger (IHX), were compared with the data tested in reactor. A good agreement between the calculated results and the test data was obtained.
Finally, the system analysis code with three-dimensional hot pool model was used to analyze the thermal-hydraulic behavior in upper plenum of "MONJU" FBR during reactor scram transient, and the flow field in CEFR hot pool under steady-state operation condition and after scram. Some thermal stratification characteristics in Monju was founded. The agreement between the computational flow field and hot pool geometry of CEFR showed the effectiveness of porous medium model. Also, some characteristic of flow field was founded.
As the extension of SAC-CFR development, an analysis code to perform thermal-hydraulic calculation in Passive Direct Reactor Auxiliary Cooling System (PDRACS) was developed through the coupling of thermal-hydraulic response in direct heat exchanger (DHX), air heat exchanger (AHX) and circuits of PDRACS. After steady-state initialization, a transient starting from air damper opening at the instant of reactor scram was simulated. Key parameters, such as mass flow rate in intermediate loop under natural circulation, heat removed by PDRACS, air temperature at AHX outlet, coolant temperature at both side of DHX, are calculated, which preliminary showed the effectiveness of the code. And the newly developed code is now ready to be incorporated into SAC-CFR to perform the interactive response between the PDRACS and the whole system after scram.
引文
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