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U.S. (2001) Nuclear Regulatory Commission. Regulatory Guide 1.190 Calculation and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. Office of Nuclear Regulatory Research.

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  • 标题: 堆芯功率分布对RPV辐照影响的分析方法研究Analysis Method Research for the Influence of Core Power Distribution on RPV Radiation

    作者: 夏春梅, 丁谦学, 梅其良

    关键字: 功率分布, 快中子注量率, 离散纵标法, 正向输运, 共轭输运Power Distribution, Fast Neutron Flux, Discrete Coordinate Method, Forward Transport, Adjoint Transport

    期刊名称: 《Nuclear Science and Technology》, Vol.4 No.3, 2016-07-13

    摘要: 堆芯功率分布决定了堆芯裂变中子和γ射线源的分布,在堆本体布置确定的情况下,堆芯功率分布成为影响反应堆压力容器(RPV)辐照安全(即RPV中的快中子(E > 1.0 MeV)注量率)的主要因素。本文基于CAP1400反应堆模型,结合使用二维离散纵标法程序DORT的正向输运和共轭输运方法,研究给出了一套能快速判断堆芯功率分布变化对RPV中最大快中子注量率影响的分析方法。该方法避免了以往需要进行反复输运计算的分析模式,只需进行一次正向输运和共轭输运计算、并辅以简单的数据处理过程,便可完成堆芯功率分布对RPV辐照影响的敏感性分析,从而能大大提高计算分析效率。 Core power distribution determines the distribution of core fission neutron and γ ray source. In the case of a certain reactor arrangement, core power distribution is the main factor that affects the radiation safety of reactor pressure vessel (RPV) (as the fast neutron (E > 1.0 MeV) flux in RPV). By combining the forward transport method with the adjoint transport method of a 2D discrete coordinate method program DORT, this paper presents a set of analysis method which can quickly judge the effect of the core power distribution change on RPV maximum fast neutron flux based on the CAP1400 reactor model. This method avoids the necessity to perform repeated transport cal-culation in the past analysis model. The sensitivity analysis for the influence of core power distri-bution on RPV radiation can be finished with one forward transport calculation and one adjoint transport calculation, as well as straightforward data process. This method can greatly improve the efficiency of calculation and analysis.

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