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Comparative Analysis of DPA Processed from Current Evaluated Nuclear Data Libraries

机译:从当前评估核数据库处理DPA的比较分析

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Recent pressure vessel surveillance reports contain DPA rates as an exposure parameter. In order to assess the reliability of the DPA data, it is useful to inter-compare available DPA data processed from current evaluated nuclear data libraries. We generated the damage energy production cross sections for elements in a RPV of a PWR and a core barrel of a LMR, with NJOY 97 code system from the currently available evaluated nuclear data libraries, ENDF/B-VI.5, JEF-2.2, JENDL-3.2, BROND-2.2, and CENDL-2.1. The DPA rates using the neutron spectra from the surveillance test of Korean PWR Ulchin Unit 1 and the design of KALIMER LMR were inter-compared. The results show a maximum relative difference of 22% for carbon steel in a PWR. The effect of partial damage cross sections such as elastic scattering, inelastic scattering and disappearance reaction has been analyzed as well as status of iron, chrome and nickel.
机译:最近的压力容器监测报告包含DPA速率作为曝光参数。为了评估DPA数据的可靠性,它对从当前评估的核数据库进行的可用DPA数据相互比较可用。我们在LMR的RPV中为元素产生了损伤能源生产横截面,其中NJOY 97代码系统来自当前可用的评估的核数据库,ENDF / B-VI.5,JEF-2.2, JENDL-3.2,BROND-2.2和CENDL-2.1。使用来自韩国PWR Ulchin单元1的监视试验的DPA速率和Kalimer LMR的设计进行了相互依赖。结果显示PWR中碳钢的最大相对差异为22%。已经分析了部分损伤横截面,例如弹性散射,无弹性散射和消失反应的影响以及铁,铬和镍的状态。

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