生成并验证基于 ENDF/B-VIII.0 的新 WIMS-D 库

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jan Malec , Oscar Cabellos , Marjan Kromar , Andrej Trkov
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引用次数: 0

摘要

WIMSD-5B 传输代码是用于核反应堆堆芯设计和燃料管理的确定性工具。它能有效处理针室和超级针室模型,并计算反应堆物理计算所必需的均质化截面。Jožef Stefan 研究所开发的 CORD-2 软件包和马德里理工大学(UPM)开发的 SEANAP 等堆芯设计软件包都使用了 WLUP。WLUP 更新项目 https://www-nds.iaea.org/wimsd 演示了用不同的已评估核数据 库更新 WIMS-D 库的方法,包括更新到 ENDF/B-VII.1 版的 ENDF 库。利用程序的更新版本,开发了基于ENDF/B-VIII.0数据的新WIMS-D库,以提高堆芯设计计算的准确性。对该库进行了多项改进,并使用一个代表典型压水堆的 3×3 超级堆芯基准模型演示了每项改进的效果。最后,还测试了该库在各种中子输运问题上的性能,以确保不出现倒退。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0
The WIMSD-5B transport code is a deterministic tool for nuclear reactor core design and fuel management. It can efficiently handle pin-cell and supercell models and calculate homogenized cross sections, which are essential for reactor physics calculations. It is used by core design packages such as the CORD-2 package, developed at the Jožef Stefan Institute, and SEANAP developed by Universidad Politécnica de Madrid (UPM). The WLUP update project https://www-nds.iaea.org/wimsd demonstrated the way to update the WIMS-D libraries with different evaluated nuclear data libraries, including ENDF libraries up to version ENDF/B-VII.1. Using an updated version of the procedure, a new WIMS-D library based on the ENDF/B-VIII.0 data was developed to improve the accuracy of core design calculations. Several improvements to the library were made and the effects of each individual improvement was demonstrated using a 3×3 supercell benchmark model that is representative of a typical pressurized water reactor. Finally, the performance of the library over a diverse set of neutron transport problems was tested for, to ensure no regressions were introduced.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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