Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION

IF 1 4区工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY

Science and Technology of Nuclear Installations Pub Date : 2022-01-05 DOI:10.1155/2022/6319628

Izza Shahid, Nadeem Shaukat, Amjad Ali, Meer Bacha, Ammar Ahmad, M. Siddique, R. Khan, Sajjad Tahir, Zeeshan Jamil

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引用次数: 1

Abstract

A typical 1100 MWe pressurized water reactor (PWR) is a second unit installed at the coastal site of Pakistan. In this paper, verification analysis of reactivity control worth by means of rod cluster control assemblies (RCCAs) for startup and operational conditions of this typical nuclear power plant (CNPP) has been performed. Neutronics analysis of fresh core is carried out at beginning of life (BOL) to determine the effect of grey and black control rod clusters on the core reactivity for startup and operating conditions. The combination of WIMS/D4 and CITATION computer codes equipped with JENDL-3.3 data library is used for the first time for core physics calculations of neutronic safety parameters. The differential and integral worth of control banks is derived from the computed results. The effect of control bank clusters on core radial power distribution is studied precisely. Radial power distribution in the core is evaluated for numerous configurations of control banks fully inserted and withdrawn. The accuracy of computed results is validated against the reference values of Nuclear Design Report (NDR) of 1100 MWe typical CNPP. It has been observed that WIMS-D4/CITATION shows its capability to effectively calculate the reactor physics parameters.

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基于WIMS/D4和CITATION的典型1100mwe核电站控制棒建模与价值计算

典型的1100兆瓦压水反应堆（PWR）是安装在巴基斯坦沿海地区的第二个机组。本文对该典型核电站（CNPP）在启动和运行条件下利用棒簇控制组件（RCCA）进行反应性控制的价值进行了验证分析。在使用寿命开始时（BOL）对新堆芯进行中子学分析，以确定灰色和黑色控制棒簇对启动和运行条件下堆芯反应性的影响。首次将配备JENDL-3.3数据库的WIMS/D4和CITATION计算机代码组合用于中子安全参数的堆芯物理计算。根据计算结果导出了控制组的微分值和积分值。精确地研究了控制组簇对堆芯径向功率分布的影响。针对完全插入和抽出的控制组的多种配置，评估堆芯中的径向功率分布。计算结果的准确性根据1100 MWe典型CNPP的核设计报告（NDR）的参考值进行了验证。据观察，WIMS-D4/CITATION显示了其有效计算反应堆物理参数的能力。

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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来源期刊

Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-

CiteScore

2.30

自引率

9.10%

发文量

审稿时长

4-8 weeks

期刊介绍： Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.