Development of adjusted nuclear data library for fast reactor application

K. Yokoyama
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引用次数: 1

Abstract

In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s. The adjusted library is called the unified cross-section set, which is an ABBN-type group constant set with 70-group energy structure. The first version was developed in 1991 and is called ADJ91. After that, ADJ98, ADJ2000, ADJ2000R, and ADJ2010 were constantly developed. For instance, ADJ2010 was developed based on JENDL-4.0, which provides covariance data needed to apply the cross-section adjustment method, by using 488 integral experimental data acquired in typical fast reactor systems. ADJ2010 has been used as the standard cross-section set for nuclear design in the fast reactor cycle technology development project (FaCT) and the succeeding fast reactor projects. In parallel, the integral experimental data were further expanded to improve the design prediction accuracy of the core loaded with MA and/or degraded Pu. Using the additional integral experimental data, development of the next version of ADJ2017 was started in 2017. In 2022, the latest unified cross-section set AJD2017R was developed based on JENDL-4.0 by using 619 integral experimental data. An overview of the latest version with a review of previous ones will be shown. On the other hand, the latest Japanese evaluated nuclear data library JENDL-5 was released at the end of 2021. In the development of JENDL-5, some of the integral experimental data used in ADJ2017R were explicitly utilized in the nuclear data evaluation. However, this is not reflected in the covariance data. This situation needs to be considered when developing a next version of the unified cross-section set based on JENDL-5. Preliminary adjustment calculation based on JENDL-5 is performed using C/E (calculation/experiment) values simply evaluated by a sensitivity analysis. The preliminary result of the JENDL-5-based adjustment will be also discussed.
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快堆应用调整核数据库的开发
日本从20世纪90年代初开始,就开始基于截面平差法开发用于快速矢量应用的调整核数据库。调整后的库称为统一截面集,是一个abbn型70基团能量结构的群常数集。第一个版本在1991年发展并且被称为ADJ91。此后,又不断开发出ADJ98、ADJ2000、ADJ2000R、ADJ2010。例如,基于JENDL-4.0开发的ADJ2010,利用在典型快堆系统中获得的488个积分实验数据,提供了应用截面调整方法所需的协方差数据。在快堆循环技术开发项目(FaCT)及后续的快堆项目中,ADJ2010已被用作核设计的标准截面集。同时,进一步扩展了积分实验数据,以提高加载MA和/或降解Pu的堆芯的设计预测精度。利用额外的积分实验数据,下一个版本的ADJ2017于2017年开始开发。2022年,利用619个积分实验数据,基于JENDL-4.0开发了最新的统一截面集AJD2017R。将显示最新版本的概述以及对以前版本的回顾。另一方面,日本最新的评估核数据库JENDL-5于2021年底发布。在JENDL-5的开发过程中,将部分在ADJ2017R中使用的积分实验数据明确用于核数据评价。然而,这并没有反映在协方差数据中。在基于JENDL-5开发下一个版本的统一截面集时,需要考虑这种情况。基于JENDL-5的初步平差计算采用简单的灵敏度分析评估的C/E(计算/实验)值。本文还将讨论基于jendl -5平差的初步结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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