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采用离散坐标DOT3.5程序计算了秦山核电二期工程反应堆主屏蔽的中子和γ射线通量密度分布、剂量率和释热率,并用中子通量密度综合方法由一维和二维计算结果得到了空间任意点的三维中子通量密度,确定了压力容器内表面的快中子注量。其计算结果均小于设计限值,符合设计要求。
The flux density distribution, dose rate and heat release rate of neutron and γ-ray of the main shielding of Qinshan Nuclear Power Station’s second-stage reactor were calculated by the discrete coordinate DOT3.5 program. The neutron flux density method was used to calculate the neutron flux and γ-ray flux density from the one-dimensional and two- The three-dimensional neutron flux density at any point in space was obtained, and the fast neutron fluence on the inner surface of the pressure vessel was determined. The calculation results are less than the design limits, in line with design requirements.