• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>International Journal of Heat and Mass Transfer >Drift-flux modeling of void fraction for boiling two-phase flow in a tight-lattice rod bundle
【24h】

Drift-flux modeling of void fraction for boiling two-phase flow in a tight-lattice rod bundle

机译：在紧密晶格杆束中沸腾两相流的空隙级分的漂移通量建模

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The concept of a resource-renewal boiling water reactor (RBWR) that uses spent nuclear fuel as a nuclear fuel has been proposed to reduce the period required for the radiotoxicity of spent nuclear fuel decaying to the same level as natural uranium ore from about 100,000 years to about 300 years. The RBWR core is designed based on the tight-lattice core concept to reduce the ratio of a moderator to fuel. Since the void fraction is one of the most critical design parameters for the RBWR, this study developed the drift-flux correlation applicable to two-phase flow in the tight-lattice rod bundle. The prediction error of the newly developed drift-flux correlation is ±11.7 %. The validated rod bundle geometrical conditions are the number of rods from 4 to 37, the rod spacing from 1.0 to 2.0 mm, the rod diameter from 9.0 to 13.7 mm, the mixture volumetric flux from 0.11 to 211 m/s, and the pressure from 0.1 to 7.2 MPa. The comparison in the distribution parameter between the tight-lattice rod bundle and the conventional BWR rod bundle indicates that the distribution parameter for the tight-lattice rod bundle is larger than that for the conventional BWR rod bundle. The increased distribution parameter in the tight-lattice core may be due to the small rod spacing and the triangular array of the rods. Both of the small rod spacing and the triangular array of the rods tend to increase the distribution parameter.
机译：已经提出了使用废核燃料作为核燃料的资源续订沸水反应器（RBWR）的概念，以减少废核燃料腐烂的无毒性毒性所需的时间，因为自然铀矿以约10万年大约300年。 RBWR芯基于紧密晶格核心概念设计，以降低主持人对燃料的比率。由于空隙率是RBWR最关键的设计参数之一，因此该研究开发了适用于紧密晶格杆束中的两相流的漂移通量相关性。新开发的漂移通量相关性的预测误差为±11.7％。验证的杆束几何条件是4至37的杆数，杆间距为1.0至2.0 mm，杆直径为9.0至13.7mm，混合体积磁通量为0.11至211 m / s，压力0.1到7.2 MPa。紧密晶格杆束之间的分布参数和传统的BWR杆束之间的比较表明，紧密晶格杆束的分布参数大于传统BWR杆束的分布参数。紧密晶格芯中的增加的分布参数可以是由于小杆间隔和杆的三角形阵列。两个小杆间隔和杆的三角形阵列倾向于增加分布参数。

著录项

  • 来源
    《International Journal of Heat and Mass Transfer》 |2021年第12期|121769.1-121769.14|共14页
  • 作者

    Takashi Hibiki; Shuichiro Miwa; Kenichi Katono;

  • 作者单位

    Department of Mechanical Engineering City University of Hong Kong 83 Tat Chee Avenue Kowloon Tong Hong Kong;

    Division of Applied Quantum Science and Engineering Graduate School of Engineering Hokkaido University North 13 West 8 Kita-ku Sapporo 060-8628 Japan Nuclear Professional School Faculty of Engineering The University ofTokyo 2-22 Shirakata Tokai-mura 319-1188 Japan;

    Hitachi-CE Nuclear Energy Ltd. 3-1-1 Saiwai-cho Hitachi Ibaraki 317-0073 Japan;

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

    Drift-flux model; Rod bundle; Tight lattice core; Void fraction; Two-phase flow;

    机译：漂移通量模型;杆束;紧密晶状体;空隙分数;两相流;

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