首页> 外文期刊>Nuclear Engineering and Design >Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor
【24h】

Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor

机译:开发用于计算WWER-1000核反应堆燃耗方面的控制棒价值的外部联接器

获取原文
获取原文并翻译 | 示例
       

摘要

One of the main problems relating to operation of a nuclear reactor is its safety and controlling system. The most widely used control systems for thermal reactors are neutron adsorbent rods. In this study a code based method has been developed for calculation of integral and differential control rod worth in terms of burn-up for a WWER-1000 nuclear reactor. External coupling of WIMSD-5B, PARCS V2.7 and COBRA-EN has been used for this purpose. WIMSD-5B has been used for cell calculation and handling burn-up of the core in various days. PARCS V2.7 has been used for neutronic calculation of core and critical boron concentration search. Thermal-hydraulic calculation has been performed by COBRA-EN. An external coupling algorithm has been developed by MATLAB to couple and transfer suitable data between these codes in each step. Steady-State Power Picking Factors (PPFs) of the core and control rod worth for different control rod groups have been calculated from Beginning Of Cycle (BOC) to 289.7 Effective Full Power Days (EFPDs) in some steps. Results have been compared with the results of Bushehr Nuclear Power Plant (BNPP) Final Safety Analysis Report (FSAR). The results show a good agreement and confirm the ability of developed coupling in calculation of control rod worth in terms of burn-up. (C) 2016 Elsevier B.V. All rights reserved.
机译:与核反应堆的运行有关的主要问题之一是其安全和控制系统。用于热反应堆的最广泛使用的控制系统是中子吸附棒。在这项研究中,已经开发了一种基于代码的方法,用于计算就WWER-1000核反应堆的燃耗而言的积分和差动控制棒价值。 WIMSD-5B,PARCS V2.7和COBRA-EN的外部耦合已用于此目的。 WIMSD-5B在许多天中已用于单元计算和处理核心的消耗。 PARCS V2.7已用于中子和临界硼浓度搜索的中子计算。热工水力计算已由COBRA-EN执行。 MATLAB开发了一种外部耦合算法,以在每个步骤中在这些代码之间耦合和传输合适的数据。在某些步骤中,已从周期开始(BOC)到289.7有效满功率日(EFPDs)计算出了不同控制棒组的核心和控制棒的稳态功率拾取因子(PPF)。将结果与布什尔核电站(BNPP)的最终安全分析报告(FSAR)的结果进行了比较。结果显示出良好的一致性,并证实了开发的联轴器在计算燃耗方面的控制杆价值的能力。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第8期|612-625|共14页
  • 作者单位

    NSTRI, Reactor Res Sch, Tehran, Iran;

    Shahid Beheshti Univ, Fac Engn, Tehran, Iran;

    NSTRI, Reactor Res Sch, Tehran, Iran;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:41:53

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号