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Development of the Method for RPV Fast Neutron Fluence Calculation

Author: ZuoYuHang
Tutor: ZhangShaoZuo；JiangXiaoFeng
School: Shanghai Jiaotong University
Course: Nuclear Energy Science and Engineering
Keywords: Pressure vessel Fluence Discrete ordinate method Neutron source The method of least squares
CLC: TL32
Type: Master's thesis
Year: 2012
Downloads: 55
Quote: 0
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Abstract


In this thesis, using the discrete ordinate (SN) to carry out the calculation of the pressure vessel neutron fluence . When the reactors to achieve their design life , due to the nuclear power plant to extend the run , for security and economic reasons , the need to make an accurate assessment of the structural integrity of the pressure vessel . The pressure vessel sustained by high-energy neutron irradiation , the material properties will be gradual deterioration , so its fast neutron fluence irradiation damage parameters that must be learned . The SN method because it can effectively solve the neutron deep penetration problems , and has a high degree of timeliness in processing reactors three-dimensional model . This thesis will NUREG / CR 6453, NUREG / CR 6115 benchmark problems fluence calculation methods of argumentation . The three-dimensional neutron fluence rate distribution of the fluence rate of two-dimensional and one-dimensional distribution of integrated neutron transport calculated by the the 2D (SN) procedure DORT and the completion of the BUGLE-96 cross-section library . In the calculation, the anisotropic scattering cross section P3 start angle using S8 orthogonal group discretization . Burnup distribution of the neutron source distribution based on the power distribution calculated includes mixed fission spectrum, power - source normalization factor , XY coordinate system to the coordinate system R-θ neutron source converter . This paper describes the development and demonstration of the source of the conversion process , the conversion error is less than 1% , to meet the computing requirements . This thesis, radial , axial , amplitude angular direction of the neutron fluence rate distribution analysis , the dosimeter of the irradiation surveillance pipe and heap outside at the neutron energy spectrum , the response rate made ??a detailed comparison of calculation results For showed that meet the requirements of the NRC RG1.190 neutron fluence calculation method is reasonable and effective . In this thesis neutron solution spectrum of the least squares method are discussed in detail . Data combined for processing , the best estimate of the neutron energy spectrum and its uncertainty can be obtained , and thus the radiation dose parameters , such as fast neutron fluence rate on the measured data and the neutron transport calculation using the least squares method ( E gt; 1.0MeV), the best estimate of the rate of the reaction can be very easy to get .

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CLC: > Industrial Technology > Nuclear technology > Engineering of Nuclear Reactors > Reactor physics and design, calculation
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