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SOURCE TERM CHARACTERIZATION METHOD AND THE SYSTEM FOR EX-CORE STRUCTURAL COMPONENTS IN A REACTOR

机译:反应器中核外结构成分的源术语表征方法和系统

摘要

PURPOSE: An apparatus and a method for evaluating the source-team of the ex-core structure of a nuclear reactor are provided to easily evaluate source-team by automating all parts. CONSTITUTION: A method for evaluating the source-team of the ex-core structure of a nuclear reactor is as follows. Neutrons are generated in the in-core of a nuclear reactor. The neutron fluxes at the in-core and the boundary area of the in-core and an ex-core structural component are calculated(S100). The reduction rate of the neutron fluxes at the ex-core structural component is calculated(S110). The actual neutron flux of each area of the ex-core structural component is calculated(S120). The source-team of each area of the ex-core structural component is calculated(S130).
机译:目的:提供一种用于评估核反应堆前核结构源团队的装置和方法,以通过使所有部件自动化来轻松地评估源团队。组成:一种评估核反应堆前核结构源团队的方法如下。中子在核反应堆的核内产生。计算核内和核外与核外结构成分边界处的中子通量(S100)。计算在核外结构成分处中子通量的减少率(S110)。计算前芯结构部件的每个区域的实际中子通量(S120)。计算前核心结构部件的每个区域的源团队(S130)。

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