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事故后安全壳内环境条件计算分析

孙婧, 马秀歌, 陈巧艳

孙婧, 马秀歌, 陈巧艳. 事故后安全壳内环境条件计算分析[J]. 南方能源建设, 2015, 2(4): 53-56. DOI: 10.16516/j.gedi.issn2095-8676.2015.04.008
引用本文: 孙婧, 马秀歌, 陈巧艳. 事故后安全壳内环境条件计算分析[J]. 南方能源建设, 2015, 2(4): 53-56. DOI: 10.16516/j.gedi.issn2095-8676.2015.04.008
Jing SUN, Xiuge MA, Qiaoyan CHEN. Computational Analysis of Environment Condition Inside Containment After Accident[J]. SOUTHERN ENERGY CONSTRUCTION, 2015, 2(4): 53-56. DOI: 10.16516/j.gedi.issn2095-8676.2015.04.008
Citation: Jing SUN, Xiuge MA, Qiaoyan CHEN. Computational Analysis of Environment Condition Inside Containment After Accident[J]. SOUTHERN ENERGY CONSTRUCTION, 2015, 2(4): 53-56. DOI: 10.16516/j.gedi.issn2095-8676.2015.04.008
孙婧, 马秀歌, 陈巧艳. 事故后安全壳内环境条件计算分析[J]. 南方能源建设, 2015, 2(4): 53-56. CSTR: 32391.14.j.gedi.issn2095-8676.2015.04.008
引用本文: 孙婧, 马秀歌, 陈巧艳. 事故后安全壳内环境条件计算分析[J]. 南方能源建设, 2015, 2(4): 53-56. CSTR: 32391.14.j.gedi.issn2095-8676.2015.04.008
Jing SUN, Xiuge MA, Qiaoyan CHEN. Computational Analysis of Environment Condition Inside Containment After Accident[J]. SOUTHERN ENERGY CONSTRUCTION, 2015, 2(4): 53-56. CSTR: 32391.14.j.gedi.issn2095-8676.2015.04.008
Citation: Jing SUN, Xiuge MA, Qiaoyan CHEN. Computational Analysis of Environment Condition Inside Containment After Accident[J]. SOUTHERN ENERGY CONSTRUCTION, 2015, 2(4): 53-56. CSTR: 32391.14.j.gedi.issn2095-8676.2015.04.008

事故后安全壳内环境条件计算分析

详细信息
    作者简介:

    孙婧(1985),女,福建福州人,工程师,学士,主要从事核电厂热工水力和事故分析研究工作(e-mai)sunjing@cnpe.cc。

  • 中图分类号: TL364

Computational Analysis of Environment Condition Inside Containment After AccidentEn

  • 摘要: 以M 310+型核电厂为例,计算分析了设计基准事故以及严重事故后安全壳内压力、温度环境条件。对核电厂设计基准事故和严重事故分析分别采用了法国的安全壳热工水力计算分析程序PAREO和一体化严重事故分析程序MAAP。计算分析给出了设计基准事故和严重事故下安全壳压力、大气温度和露点温度的峰值随时间变化曲线。计算结果表明设计基准事故和严重事故后,安全壳压力峰值工况均以MSLB为始发事故;设计基准事故后安全壳压力峰值为0.511 8 MPa,严重事故后安全壳压力峰值为0.602 MPa。
    Abstract: The pressure and tempereature inside containment after both design basis accidents and severe accidents are calculated and anaylzed based on M 310+ NPP. Design basis accidents are calculated by French containment thermal hydraulic analysis code PAREO and severe accidents are calculated by integrated severe accident analysis code MAAP. The containment peak pressure, atomosphere and dew peak temperature of desigan basis accident and severe accident are calculated and shown. The results show that both design basis and severe accidents containment peak pressure conditions are induced by MSLB accident, that the peak containment pressure after design basis accidents is 0.511 8 MPa and after severe accidents is 0.602 MPa.
  • 图  1   PAREO程序节点图

    Figure  1.   Nodalization of PAREO Code

    图  2   MAAP一回路节点图

    Figure  2.   Nodalization of Primary System of MAAP Code

    图  3   MAAP安全壳控制体划分图

    Figure  3.   Nodalization of Containment of MAAP Code

    图  4   安全壳压力

    Figure  4.   Containment Pressure

    图  5   安全壳大气、露点、地坑水温度

    Figure  5.   Atmosphere,Pew and Sump Temperature of Containment

    图  6   MSLB严重事故后安全壳内压力

    Figure  6.   Containment Pressure During MSLB Severe Accident

    图  7   MSLB严重事故后安全壳内温度

    Figure  7.   Containment Temperature During MSLB Severe Accident

    表  1   MSLB事故下安全壳压力温度峰值计算结果(一只给水控制阀失效)

    Table  1   Containment Peak Pressure and Temperature After MSLB Basis Aaccidents with Failure of One Main Feedwater Control Valve

    功率/% 压力/MPa 大气温度/℃ 地坑水温度/℃ 露点温度/℃
    102 0.511 6 189.8 130.3 139.9
    75 0.511 8 186.9 130.8 140.1
    50 0.507 184.6 130.6 139.8
    25 0.502 181.3 130.0 139.3
    0 0.503 178.7 129.2 139.5
    下载: 导出CSV

    表  2   严重事故序列进程

    Table  2   Severe Accident Sequences

    事故进程 1 2 3 4
    SBO LLOCA SLOCA MSLB
    事故开始 0 0 0 0
    堆芯裸露 7 618 10 1 825 5 724
    堆芯出口温度达到650 ℃ 8 552 1 085 2 354 6 515
    燃料包壳快速氧化 15 080 1 750 5 881 18 396
    过滤排放系统第一次开启 86 400 86 400 86 400 86 400
    过滤排放系统第一次关闭 221 100 184 100
    过滤排放系统第二次开启 246 700
    喷淋开启 259 200 259 200 259 200 259 200
    过滤排放系统第二次关闭 259 700 259 700 259 700
    下载: 导出CSV

    表  3   MSLB事故始发设计基准事故和严重事故对比

    Table  3   Comparison of Design Basis Accident and Severe Accident Induced by Mslb Accident

    工况 压力峰值/MPa 压力峰值时间/s 大气温度峰值/℃ 温度峰值时间/s 计算结束时间/s 峰值形成原因
    设计基准事故 0.511 8 348 189.8 80 590 破口向安全壳喷放
    严重事故 0.602 86 400 196 86 400 259 200 24 h时过滤排放系统开启
    下载: 导出CSV
  • [1] HAF 102—2004,核动力厂设计安全规定[S].
    [2] 朱继洲. 核反应堆安全分析 [M]. 北京:原子能出版社,2004.
    [3] 臧希年. 核电厂系统及设备 [M]. 北京:清华大学出版社,2003.
    [4] 陈松,刘鑫,史国宝,等. 严重事故下安全壳内环境条件计算分析 [J]. 核动力工程,2006,1(增刊):14-17.

    CHEN Song, LIU Xin, SHI Guobao, et al. Computational Analysis of Environment Condition Inside Containment under Severe Accident [J]. Nuclear Power Engineering,2006,1(Supp.1):14-17.

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出版历程
  • 收稿日期:  2015-11-09
  • 刊出日期:  2015-12-24

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    Qiaoyan CHEN

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