...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Annals of nuclear energy >Research on the fuel loading patterns of the initial core in Chinese pebble-bed reactor HTR-PM
【24h】

Research on the fuel loading patterns of the initial core in Chinese pebble-bed reactor HTR-PM

机译：中国卵石床反应堆HTR-PM初始堆芯燃料加载方式研究

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

Modular high-temperature gas-cooled reactor (HTGR) is a kind of safe and advanced nuclear energy system, which can provide electric power and high-temperature process-heat efficiently. At present, a 200 MWe demonstration plant, named high-temperature gas-cooled reactor - pebble-bed module (HTR-PM), is being built in China and is planned to be critical in one or two years. In this paper, the physical consideration on the fuel loading patterns of the initial core of HTR-PM is given, and the initial core of HTR-PM is proposed to be made up of low-enrichment fuel spheres and graphite spheres. Then several representative schemes are simulated using VSOP code. The relationship between the key physical parameters (fuel enrichment, flux distribution, temperature coefficient, power per fuel sphere, charging rate) and the volume fraction of fuel spheres in the initial core is analyzed. As a result, the feasible region of the volume fraction of fuel spheres in the initial core is determined as [5/15, 11/15]. The work of this paper can provide support for the fuel management of HTR-PM in the future. (C) 2018 Elsevier Ltd. All rights reserved.
机译：模块化高温气冷堆（HTGR）是一种安全，先进的核能系统，可以有效地提供电力和高温过程热。目前，中国正在建设一个200 MWe的示范工厂，称为高温气冷堆-卵石床模块（HTR-PM），并计划在一两年内变得至关重要。在本文中，对HTR-PM初始堆芯的燃料装载方式进行了物理考虑，并提出HTR-PM的初始堆芯由低浓燃料球和石墨球组成。然后使用VSOP代码模拟了几种代表性方案。分析了关键物理参数（燃料富集，通量分布，温度系数，每个燃料球的功率，充气速率）与初始堆芯中燃料球的体积分数之间的关系。结果，初始芯中的燃料球的体积分数的可行区域被确定为[5 / 15、11 / 15]。本文的工作可以为将来HTR-PM的燃料管理提供支持。 （C）2018 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2018年第8期|235-240|共6页
  • 作者

    Zhang Jingyu; Guo Jiong; Li Fu; Sun Yuliang;

  • 作者单位

    North China Elect Power Univ, Sch Nucl Sci & Engn, Beijing 102206, Peoples R China;

    Minist Educ, Key Lab Adv Reactor Engn & Safety, Beijing 100084, Peoples R China;

    Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China;

    Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Fuel loading patterns; The initial core; Pebble-bed reactor; HTR-PM;

    机译：燃料装载方式;初始堆芯;卵石床反应堆;HTR-PM;

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