During the simulation of AP1000 nuclear power plant,the values of input parameters, core nodalization methods and calculation models, may have important influence on the code outputs. Therefore, it is necessary to ide...During the simulation of AP1000 nuclear power plant,the values of input parameters, core nodalization methods and calculation models, may have important influence on the code outputs. Therefore, it is necessary to identify and evaluate the influence of these parameters and modeling approaches quantitatively. Based on the best estimate thermal-hydraulic system code RELAP5,sensitivity analyses have been performed on core partition methods,parameters and models in AP1000 nuclear power plant,such as the core channel number,pressurizer node number,and feedwater temperature. The results show that code channel number,code channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop in the reactor. The feedwater temperature is a sensitive factor to the steam generator( SG) outlet temperature and the SG outlet pressure. In addition,the influence of the cross-flow model on coolant temperature variation and pressure drop through the reactor is insignificant,both in steady state and loss of power transient. Furthermore, some suitable parameters and modes also have been put forward for the nuclear system simulation.展开更多
The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by...The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by shrinkage and shearing work to increase the spare fuel lattice number. In order to solve the problem of shrinkage and shearing work of spent fuel involving the problem of radioactive safety, the radioactive source item is calculated by ORIGEN2 program base on Unit 1 Ⅱ of Lingao Nuclear Power Plant(NPP), and the radiation dose rate of the related component shrinkage operation scene is simulated by the MCNP5 program. In addition, the effectiveness of shielding measures is discussed, and the maximum dose rate is within 0.35 μSv/h at the distance of 2.5 m from component center, and the maximum dose rate is almost 0 at the distance of 3.2 m from the component center. The intensity of the radiation dose produced by the related components is very low and can be neglected, which belong to the green area of NPP. The program calculation system from source term calculation to shielding calculation is established, and an engineering example is referenced, and its application and analysis are carried out. It provides a basis for radioactive safety analysis and evaluation for the shrinkage operation of spent fuel and makes the shrinkage technology of fuel-related components safer and more reliable.展开更多
This work presents a new method for preparation of samarium alloy. Using A1 rod as anode, electrochemical formation of Sm-A1 alloy on Mo electrode from Sm203 in LiC1- KC1-MgC12-KF molten salts was investigated. Samari...This work presents a new method for preparation of samarium alloy. Using A1 rod as anode, electrochemical formation of Sm-A1 alloy on Mo electrode from Sm203 in LiC1- KC1-MgC12-KF molten salts was investigated. Samarium mainly exists in the form of A12Sm in Li-Mg matrix, and the concentration of Sm in this alloy runs up to be as high as 34.7%. The reaction of samarium preparation appears like a replacement reaction. The new preparation method makes possible a high samarium content in electrochemical deposition of Sm-A1 alloy. Using A1 rod as anode consumedly decreased, the electrolytic cell voltage, and facilitated Sm deposition from Sm203. This preparation method uses 8m203 as raw materials to gain samarium alloy directly, which could revolutionize the industrial production of samarium alloys.展开更多
文摘During the simulation of AP1000 nuclear power plant,the values of input parameters, core nodalization methods and calculation models, may have important influence on the code outputs. Therefore, it is necessary to identify and evaluate the influence of these parameters and modeling approaches quantitatively. Based on the best estimate thermal-hydraulic system code RELAP5,sensitivity analyses have been performed on core partition methods,parameters and models in AP1000 nuclear power plant,such as the core channel number,pressurizer node number,and feedwater temperature. The results show that code channel number,code channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop in the reactor. The feedwater temperature is a sensitive factor to the steam generator( SG) outlet temperature and the SG outlet pressure. In addition,the influence of the cross-flow model on coolant temperature variation and pressure drop through the reactor is insignificant,both in steady state and loss of power transient. Furthermore, some suitable parameters and modes also have been put forward for the nuclear system simulation.
基金Supported by the Project of Radiation Shielding Calculation Based on Unit 1 Ⅱ of Lingao Nuclear Power Plant of China
文摘The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by shrinkage and shearing work to increase the spare fuel lattice number. In order to solve the problem of shrinkage and shearing work of spent fuel involving the problem of radioactive safety, the radioactive source item is calculated by ORIGEN2 program base on Unit 1 Ⅱ of Lingao Nuclear Power Plant(NPP), and the radiation dose rate of the related component shrinkage operation scene is simulated by the MCNP5 program. In addition, the effectiveness of shielding measures is discussed, and the maximum dose rate is within 0.35 μSv/h at the distance of 2.5 m from component center, and the maximum dose rate is almost 0 at the distance of 3.2 m from the component center. The intensity of the radiation dose produced by the related components is very low and can be neglected, which belong to the green area of NPP. The program calculation system from source term calculation to shielding calculation is established, and an engineering example is referenced, and its application and analysis are carried out. It provides a basis for radioactive safety analysis and evaluation for the shrinkage operation of spent fuel and makes the shrinkage technology of fuel-related components safer and more reliable.
基金supported by the National Natural Science Foundation of China (Grant No.21173060)the Basic Research Foundation of Harbin Engineering University of China (No.HEUFT08030)
文摘This work presents a new method for preparation of samarium alloy. Using A1 rod as anode, electrochemical formation of Sm-A1 alloy on Mo electrode from Sm203 in LiC1- KC1-MgC12-KF molten salts was investigated. Samarium mainly exists in the form of A12Sm in Li-Mg matrix, and the concentration of Sm in this alloy runs up to be as high as 34.7%. The reaction of samarium preparation appears like a replacement reaction. The new preparation method makes possible a high samarium content in electrochemical deposition of Sm-A1 alloy. Using A1 rod as anode consumedly decreased, the electrolytic cell voltage, and facilitated Sm deposition from Sm203. This preparation method uses 8m203 as raw materials to gain samarium alloy directly, which could revolutionize the industrial production of samarium alloys.
