Sensitivity Analysis of Relap5 Simulation on AP1000 Nuclear Power Plant

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.

Effects of interstitial cluster mobility on dislocation loops evolution under irradiation of austenitic steel

The evolution of dislocation loops in austenitic steels irradiated with Fe^(+)is investigated using cluster dynamics(CD)simulations by developing a CD model.The CD predictions are compared with experimental results in the literature.The number density and average diameter of the dislocation loops obtained from the CD simulations are in good agreement with the experimental data obtained from transmission electron microscopy(TEM)observations of Fe~+-irradiated Solution Annealed 304,Cold Worked 316,and HR3 austenitic steels in the literature.The CD simulation results demonstrate that the diffusion of in-cascade interstitial clusters plays a major role in the dislocation loop density and dislocation loop growth;in particular,for the HR3 austenitic steel,the CD model has verified the effect of temperature on the density and size of the dislocation loops.

Study on the Elman Neural Network Operation Control Strategy of the Central Air Conditioning Chilled Water System

The stable operation of the central air conditioning water system always is a major difficulty for the control profession. Paper focus on the water system with multi variable, strong coupling, nonlinear, large time delay characteristics, presented use feed forward coupling compensation method, to eliminate the coupling effect between temperature and pressure. In this paper, the Elman neural network controller is designed for the first time, and the simulation results show that the response time of Elman neural network controller is shorter, the system is more stable and the overshoot is small.

Estimation of the Dose Rate of Spent Fuel-Related Components of Lingao Nuclear Power Plant Using ORIGEN2 and MCNP5

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.

A new electrochemical preparation method for formation Sm-Al alloys on inert Mo electrode from Sm_2O_3 in LiCl-KCl-MgCl_2 -KF molten salts

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.