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随着计算能力的发展,三维离散纵标方法(SN)已逐渐为反应堆辐射屏蔽计算的主流方法之一。本文就三维SN方法应用于反应堆的精细化屏蔽建模与分析的关键问题进行了研究,主要包括精细化几何建模、堆芯固定源模型的创建和数据库截面参数敏感性分析等内容。在此基础上,本文以典型的压水反应堆为对象,构建了精细的三维SN计算分析模型,以压力容器快中子注量率为算例,完整实现了反应堆的精细化三维SN建模与分析,并将三维SN结果和蒙特卡罗方法的计算结果进行了比较分析。对比结果表明,精细化三维SN方法具有较高的计算精度,验证了三维SN方法在反应堆精细屏蔽计算问题中的有效性和正确性。
With the development of computing power, the three-dimensional discrete ordinate method (SN) has gradually become one of the mainstream methods for reactor radiation shielding calculation. In this paper, the key issues of the three-dimensional SN method applied to the modeling and analysis of the fine shielding of the reactor are studied, including the detailed geometric modeling, the establishment of the core fixed source model and the sensitivity analysis of the database section parameters. On this basis, a typical three-dimensional SN calculation and analysis model is constructed for a typical PWR reactor. Taking the fast neutron flux rate of a pressure vessel as an example, the three-dimensional SN modeling of the reactor is fully realized The results of three-dimensional SN analysis and Monte Carlo method are compared and analyzed. The comparison results show that the refined three-dimensional SN method has higher computational accuracy and validates the validity and correctness of the three-dimensional SN method in the calculation of reactor fine shielding.