使用fendl3.1 d库计算铀辐射加热的不准确性

A. Kovalev, R. Rodionov, D. Portnov, Yu. A. Kashchuk
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引用次数: 0

摘要

对中子辐射作用下的铀辐射加热结果进行了分析。利用FENDL 3.1d和ENDF核数据库对铀235和铀238进行辐射加热模拟的结果存在差异。同时,计算模型中的所有初始数据,即中子能谱、裂变材料质量、几何形状和周围结构组成都是相同的。在工作过程中,使用不同的库对铀电池的能量释放计算结果进行了比较。对试验单元的辐射加热结果进行了分析评价。所获得的数据表明FENDL 3.1d核数据库中的中子kerma因子值有误。聚变评估核数据库是由原子能机构核数据科工作组于1990年代中期创建的。FENDL专注于聚变工厂的设计以及IFMIF等材料测试工厂的应用。扩展的应用需要向库中添加一些材料,将能量范围扩展到更高的能量,并添加由带电粒子引起的反应的数据。3.1d版本于2018年1月发布,广泛用于实验核聚变反应堆ITER和示范核聚变反应堆DEMO的结构材料核分析。这项工作的结果已提交给ITER国际组织联络小组,以便向FENDL库的开发人员进行介绍。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
INACCURACIES IN THE RADIATION HEATING CALCULATIONS OF URANIUM USING FENDL 3.1D LIBRARY
The work is devoted to the analysis of uranium radiation heating results under the action of neutron radiation. The revealed results discrepancies in the radiation heating modeling of the uranium 235 and 238 using FENDL 3.1d and ENDF nuclear data libraries motivate the study. At the same time, all initial data in the computational model, namely, the neutrons energy spectrum, mass of fissile material, geometry and surrounding structures composition were identical. In the course of the work, the results of energy release calculations in uranium cells were compared using various libraries. Analytical evaluation of the radiation heating results in test cells is given. The obtained data indicate erroneous values of neutron kerma factors in FENDL 3.1d nuclear data library. Fusion Evaluated Nuclear Data Library was created by the working group of the Nuclear Data Section of the IAEA in the mid-1990s. FENDL is focused on application in the design of fusion plants as well as plants for materials testing such as IFMIF. The expanded application required the addition of some materials to the library, the expansion of the energy range to higher energies and the addition of data for reactions caused by charged particles. Version 3.1d was released in January 2018 and is widely used in nuclear analysis of structural materials for the experimental fusion reactor ITER and the demonstration fusion reactor DEMO. The results of this work have been submitted to the ITER International Organization contact group for presentation to the developers of the FENDL library.
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