用于核电站严重事故下安全壳消氢的设计方法

Design method for dehydrogenating containment of nuclear power station under serious accident

Abstract

The invention belongs to a nuclear power station system design technology, and in particular relates to a design method for dehydrogenating a containment of a nuclear power station under a serious accident. The method comprises the following steps of: selecting large break loss of coolant accident (LBLOCA), small break loss of coolant accident (SBLOCA) and station blackout (SBO) as a typical serious accident sequence; according to the serious accident sequence, modeling by using an MELCOR program, and calculating hydrogen generation amount and hydrogen concentration distribution; according to the hydrogen generation amount and the hydrogen concentration distribution, selecting a typical position for initial point distribution of a non-kinetic hydrogen recombiner; performing thermal impact analysis on the hydrogen recombiner to determine specific arrangement principles and requirements of the hydrogen recombiner; and analyzing and calculating a dehydrogenation effect of an initial point distribution scheme of the hydrogen recombiner to determine a final power distribution scheme. In the invention, a containment non-kinetic hydrogen recombiner system can be arranged reasonably, and the method is used for controlling a hydrogen risk of the containment under the serious accident, so that the integrity of the containment serving as a third protective screen is ensured.
本发明属于核电站系统设计技术,具体涉及一种用于核电站严重事故下安全壳消氢的设计方法。该方法选取一回路管道大破口、一回路管道小破口、全厂断电作为典型的严重事故序列,以此为依据采用MELCOR程序建模,计算产氢量、氢气浓度分布,根据产氢量、氢气浓度分布,选取典型位置进行非能动氢复合器的初步布点,对氢复合器进行热影响分析,确定氢复合器的具体布置原则和要求,并对氢复合器的初步布点方案进行消氢效果分析计算,确定最终的布点方案。本发明能够合理的设置安全壳非能动氢复合器系统,用于控制严重事故下安全壳的氢气风险,从而保证第三道屏障——安全壳的完整性。

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Patent Citations (2)

    Publication numberPublication dateAssigneeTitle
    CN-1838333-ASeptember 27, 2006大亚湾核电运营管理有限责任公司Severe accident diagnosis and handling method for pressurized-water reactor nuclear power station
    US-5733520-AMarch 31, 1998Asea Brown Boveri AgMethod and device for the extraction of the condenser exhaust gases of a boiling water reactor

NO-Patent Citations (8)

    Title
    《中国优秀硕士学位论文全文数据库(电子期刊)工程科技II辑》 20080815 尹峰 秦山二期扩建工程严重事故下安全壳内消氢措施的研究 31,44,45,47 1-8 , 第8期
    《中国博士学位论文全文数据库(电子期刊)工程科技II辑》 20110415 邓坚 大型干式安全壳严重事故条件下氢气控制研究 中国学术期刊(光盘版)电子杂志社 23,24,25,35,39,49,50,100 1-8 , 第4期
    《核动力工程》 20051031 孙永滨 田湾核电站物项的安全分级 519 3 第26卷, 第5期
    《核动力工程》 20051231 张世顺,孙吉良,肖岷 大亚湾核电站安装氢气复合器方案计算分析 52-54 1-8 第26卷, 第6期
    孙永滨: "田湾核电站物项的安全分级", 《核动力工程》, vol. 26, no. 5, 31 October 2005 (2005-10-31), pages 519
    尹峰: "秦山二期扩建工程严重事故下安全壳内消氢措施的研究", 《中国优秀硕士学位论文全文数据库(电子期刊)工程科技II辑》, no. 8, 15 August 2008 (2008-08-15)
    张世顺,孙吉良,肖岷: "大亚湾核电站安装氢气复合器方案计算分析", 《核动力工程》, vol. 26, no. 6, 31 December 2005 (2005-12-31), pages 52 - 54
    邓坚: "大型干式安全壳严重事故条件下氢气控制研究", 《中国博士学位论文全文数据库(电子期刊)工程科技II辑》, no. 4, 15 April 2011 (2011-04-15)

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