首页> 外文期刊>Nuclear Engineering and Design >Preliminary experiment design of graphite dust emission measurement under accident conditions for HTGR
【24h】

Preliminary experiment design of graphite dust emission measurement under accident conditions for HTGR

机译:高温气冷堆事故工况下石墨粉尘排放测量的初步实验设计

获取原文
获取原文并翻译 | 示例
           

摘要

The graphite dust movement behavior is significant for the safety analyses of high-temperature gas cooled reactor (HTGR). The graphite dust release for accident conditions is an important source term for HTGR safety analyses. Depressurization release tests are not practical in HTGR because of a radioactivity release to the environment. Thus, a theoretical analysis and similarity principles were used to design a group of modeling experiments. Modeling experiments for fan start-up and depressurization process and actual experiments of helium circulator start-up in an HTGR were used to predict the rate of graphite dust resuspension and the graphite dust concentration, which can be used to predict the graphite dust release during accidents. The modeling experiments are easy to realize and the helium circulator start-up test does not harm the reactor system or the environment, so this experiment program is easily achieved. The revised Rock'n'Roll model was then used to calculate the AVR reactor release. The calculation results indicate that the total graphite dust releases during a LOCA will be about 0.65 g in AVR. (C) 2017 Elsevier B.V. All rights reserved.
机译:石墨粉尘的移动行为对于高温气冷堆(HTGR)的安全性分析非常重要。用于事故工况的石墨粉尘释放是HTGR安全分析的重要来源。降压释放测试在HTGR中不可行,因为有放射性释放到环境中。因此,使用理论分析和相似性原理设计了一组建模实验。利用HTGR中风机启动和降压过程的建模实验以及氦循环器启动的实际实验来预测石墨粉尘的重悬率和石墨粉尘浓度,从而可以预测事故期间石墨粉尘的释放。 。建模实验易于实现,氦气循环器启动测试不会损害反应堆系统或环境,因此该实验程序很容易实现。修改后的Rock'n'Roll模型随后用于计算AVR反应堆释放量。计算结果表明,在LOCA期间,AVR中释放的石墨粉尘总量约为0.65 g。 (C)2017 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2017年第5期|218-227|共10页
  • 作者单位

    Tsinghua Univ, Inst Nucl & New Energy Technol, Adv Nucl Energy Technol Cooperat Innovat Ctr, Key Lab Adv Nucl Engn & Safety,Minist Educ, Beijing 100084, Peoples R China;

    Tsinghua Univ, Inst Nucl & New Energy Technol, Adv Nucl Energy Technol Cooperat Innovat Ctr, Key Lab Adv Nucl Engn & Safety,Minist Educ, Beijing 100084, Peoples R China;

    Tsinghua Univ, Inst Nucl & New Energy Technol, Adv Nucl Energy Technol Cooperat Innovat Ctr, Key Lab Adv Nucl Engn & Safety,Minist Educ, Beijing 100084, Peoples R China;

    Tsinghua Univ, Inst Nucl & New Energy Technol, Adv Nucl Energy Technol Cooperat Innovat Ctr, Key Lab Adv Nucl Engn & Safety,Minist Educ, Beijing 100084, Peoples R China;

    Tsinghua Univ, Minist Educ, Key Lab Thermal Sci & Power Engn, Ctr Combust Energy, Beijing 100084, Peoples R China;

  • 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

    HTGR; Graphite dust; Accident condition; Loss of coolant accident (LOCA); Resuspension; Radioactive releases;

    机译:高温气冷堆;石墨粉尘;事故情况;冷却液事故损失(LOCA);悬浮液;放射性释放;

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