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- Type of Document: M.Sc. Thesis
- Language: Farsi
- Document No: 42981 (46)
- University: Sharif University of Technology
- Department: Energy Engineering
- Advisor(s): Vosoughi, Naser
- Abstract:
- Neutron fluctuations in both low and high power reactors provide important information about the system. The origins of these fluctuations are different in both regimes. In low power the branching process is the reason of these fluctuations. But the random nature of technological processes such as boiling in the reactors cooling and mechanical structure vibrating such as control rod and fuel rod created the neutron noise. Mathematical descriptions and applications of neutron noise for each mode are different. In common mode, fluctuations in the neutron detection system, determine some parameters and determin the start abnormality in system. In this study the spatial dependence of the cross sections from neutron noise that measured at discrete points in space. These fluctuations are sources of noise. In this method it is assumed that the spatial dependence of cross sections is unknown and to reconstruction the noise revsere of integral equation for neutron cross sections fluctuations are used. The main advantage of this method is its ability to use various noise sources in the reactor and use the results without community knowledge to noise explanation and directly display of the results to operator. Whereas, precision of this type of noise because of the approximations used in reverse remodeling of the building is less than traditional methods. The aim of this research is to design software that can determine the type of noise inside the Bushehr VVER-1000 reactor. This research process is divided into two basic steps. First, using a triangular mesh size and two group noise equations of two types of common noise sources in reactor cores have been simulated. For validation of results from different methods are used, all of them imply a high performance of noise simulator software package with a triangular mesh, which is named BTRIDYN-I. In the next step, using three different methods, including inverse method, direct method and 2-D Fourier transform to investigate the type of noise has been happening inside the reactor. For better analysis of results from noise calculations by BTRIDYN-I, different scenarios were designed in VVER-1000 core. Results of the noise source reconstruction to characterization the noise generated in the reactor showed high accuracy and precision of the calculations
- Keywords:
- Vodo-Vodyanoi Energetichesky (VVER)1000 ; Neutron Noise ; Bushehr Nuclear Power Plant ; Noise Characterization ; Vibrational Absorber Noise ; Reactor Core Triangular Meshes
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