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【实习课题 1】

 

实习题目：

对堆芯材料碳化硼与不锈钢共晶行为机理的研究

Study on the mechanism of eutectic behavior of reactor core materials (boron carbide-stainless steel)

 

实习内容：

反应堆严重事故下碳化硼-不锈钢共晶反应会使控制棒过早失效，对反应堆严重事故评估影响显著，因此本实验旨在研究反应堆中吸收棒的碳化硼与结构材料不锈钢间的共晶反应机理，利用可视化高温反应炉探究反应温度、接触面压强、接触面几何形状等不同因素对于碳化硼-不锈钢共晶反应速率的影响。在得出实验数据后，利用移动粒子半隐式方法（MPS）对不同实验参数下的碳化硼-不锈钢共晶反应过程进行数值模拟，验证MPS方法对于碳化硼-不锈钢共晶反应模拟的适用性并尝试建立碳化硼-不锈钢共晶反应模型。

The eutectic reaction between boron carbide and stainless steel will cause premature failure of control rods under severe reactor accidents, which has a significant impact on the assessment of severe reactor accidents. Therefore, this experiment aims to study the eutectic reaction mechanism between absorber rod material (boron carbide) and structural material (stainless steel) in the reactor. A visualized high temperature reactor is used to investigate the effects of different factors such as reaction temperature, contact surface pressure, and contact geometry on the rate of eutectic reaction between boron carbide and stainless steel. After obtaining the experimental data, the numerical simulation of the eutectic reaction process between boron carbide and stainless steel under different experimental parameters is carried out by using the moving particle semi-implicit method (MPS) to verify the applicability of the MPS method to the simulation of boron carbide-stainless steel and to try to establish a model of the eutectic reaction between boron carbide and stainless steel.

 

企业导师：成松柏  教授

校内导师：贺秀杰  副教授  hexiujie@mail.sysu.edu.cn

 

实习补贴：3000RMB/月

 

 

【实习课题 2】

 

实习题目：

液态金属池中放射性裂变产物气溶胶洗涤研究

Study on Aerosol Scrubbing of Radioactive Fission Products in Liquid Metal Pools

 

实习内容：

在液态金属堆中，若出现燃料棒失效等严重事故，可能会导致固体裂变产物夹带在气体中一起被释放到冷却剂池中。载有放射性气溶胶的气泡在冷却剂池中不断上升至池表面覆盖气体区域，这一过程会发生复杂的热工水力学现象，同时一部分气溶胶会被去除。该研究旨在利用python等编程软件，实现对液态金属堆池洗放射性气溶胶效果的数值模拟计算与理论分析，并通过与真实实验数据对比验证，实现对最贴近实际情况的气溶胶池洗模型的建立。

In liquid metal reactors, serious accidents such as fuel rod failure may result in solid fission products being entrained in the gas and released into the coolant pool. Bubbles containing radioactive aerosols continuously rise in the coolant pool to the gas covered area on the pool surface, which leads to complex thermodynamic and hydraulic phenomena, and some aerosols are removed. The purpose of this study is to use programming software such as Python to achieve numerical simulation and theoretical analysis of the effectiveness of liquid metal reactor pool scrubbing radioactive aerosols. By comparing and verifying with real experimental data, the establishment of the aerosol pool scrubbing model that is closest to the actual situation is achieved.

 

企业导师：成松柏  教授

校内导师：刘晓星  副教授  liuxx85@mail.sysu.edu.cn

 

实习补贴： 2000元/月

 

 

【实习课题 3】

 

实习题目：

基于CFD-DEM方法对钠冷快堆严重事故下的碎片床堆积过程的数值模拟研究

Numerical simulation of debris bed accumulation process at severe accident of sodium-cooled fast reactor based on the CFD-DEM method

 

实习内容：

钠冷快堆堆芯解体事故发生后，堆芯内的堆芯熔融物将会释放出来，与冷却剂发生相互作用，碎化、沉降和堆积在压力容器下腔室或其上方的堆芯捕集器上，形成碎片床。如未及时排出碎片床的剩余衰变热，碎片床发生重熔将进一步熔穿下腔室，造成严重的后果。因此，有必要全面地研究碎片床的堆积机理以提升其冷却能力的评估。本研究基于CFD-DEM流固耦合数值方法，对钠冷快堆严重事故下的碎片床堆积过程进行了数值模拟，验证CFD-DEM方法对钠冷快堆严重事故下碎片床堆积行为模拟的适用性及预测模型的可靠性，如可能将对经验模型进行修正或开发新的经验模型。

After the core disruptive accident of sodium-cooled fast reactor (SFR), the corium inside the core will be released, interact with the coolant, fragment, settle and accumulate in the lower plenum of the pressure vessel or on the core catcher, forming a debris bed. If the remaining decay heat in the debris bed is not discharged in time, remelting of the debris bed will further melt through the lower plenum, resulting in severe consequences. Therefore, it is necessary to comprehensively investigate the mechanism of the debris bed accumulation to improve the evaluation of its cooling capacity. Based on the fluid-structure coupling numerical method of CFD-DEM, this study simulates the debris bed accumulation process under severe accident of sodium-cooled fast reactor, and verifies the applicability of CFD-DEM method to simulate the debris bed accumulation behavior under severe accident of sodium-cooled fast reactor and the reliability of the prediction model. If possible, the empirical model will be modified or a new empirical model will be developed.

 

企业导师：成松柏  教授

校内导师：杨卫岐  副教授  yangweiqi@mail.sysu.edu.cn

 

实习补贴：3000元/月

 

 

【实习题目 4】

 

实习题目：

液态金属燃料反应堆流动传热特性的数值研究

Numerical study of flow and heat transfer characteristics of liquid metal reactor

 

实习内容：

第四代核反应堆如铅冷快堆为了安全性考虑采用液态金属流体进行热量的传递，但也给模拟计算带来一定挑战。本实习调研已有的模拟方法和开展的实验工作，拟采用直接数据模拟或者大涡模拟方法建立一些工况的可靠的计算数据库，然后对传热湍流传热过程采用非线性湍流模式进行相应修改，建立更可靠的工程湍流模拟方法。

Fourth-generation nuclear reactors, such as lead-cooled fast reactors, use liquid metal fluids for heat transfer for safety considerations, but they also bring certain challenges to the calculation work. This internship investigates the current simulation methods and experimental work, and  use direct numerical simulation or large eddy simulation methods to establish a reliable database under certain working conditions. The data is used to modify the nonlinear algebraic turbulence mode in the heat transfer process accordingly to establish a more reliable engineering turbulence simulation method.

 

企业导师：程辉  副教授

校内导师：李万爱  副教授  liwai@mail.sysu.edu.cn

 

实习补贴：2000元 /月