|本期目录/Table of Contents|

[1]杨 奥,黄志翱,缪惠芳*,等.CPR1000全厂断电事故模拟及主泵轴封破口敏感性分析[J].厦门大学学报(自然科学版),2018,57(05):629-633.[doi:10.6043/j.issn.0438-0479.201803029]
 YANG Ao,HUANG Zhiao,MIAO Huifang*,et al.Simulation of Station Blackout Accident for CPR1000 and Sensitivity Analysis of Main Pump Seal Loss-of-coolant Accident[J].Journal of Xiamen University(Natural Science),2018,57(05):629-633.[doi:10.6043/j.issn.0438-0479.201803029]
点击复制

CPR1000全厂断电事故模拟及主泵轴封破口敏感性分析(PDF/HTML)
分享到:

《厦门大学学报(自然科学版)》[ISSN:0438-0479/CN:35-1070/N]

卷:
57卷
期数:
2018年05期
页码:
629-633
栏目:
研究论文
出版日期:
2018-09-27

文章信息/Info

Title:
Simulation of Station Blackout Accident for CPR1000 and Sensitivity Analysis of Main Pump Seal Loss-of-coolant Accident
文章编号:
0438-0479(2018)05-0629-05
作者:
杨 奥黄志翱缪惠芳*李 宁
厦门大学能源学院,福建 厦门 361102
Author(s):
YANG AoHUANG ZhiaoMIAO Huifang*LI Ning
College of Energy,Xiamen University,Xiamen 361102,China
关键词:
CPR1000 全厂断电 主泵轴封破口 敏感性分析
Keywords:
CPR1000 station blackout seal loss-of-coolant accident sensitivity analysis
分类号:
F 407.23
DOI:
10.6043/j.issn.0438-0479.201803029
文献标志码:
A
摘要:
全厂断电事故是导致核电厂发生严重后果的重要事件之一.采用模块化事故分析程序对CPR1000全厂断电事故进行建模与分析,计算一回路压力、压力容器水位、堆芯温度等参数,详细分析了事故进程.分析结果显示:全厂断电事故会导致反应堆压力容器在高压下失效,这将会有安全壳直接加热的风险; 同时,事故过程中会产生大量氢气,这部分氢气会逐步迁移到安全壳或者辅助厂房中,从而带来氢气爆炸的风险.针对全厂断电时主泵容易出现轴封破口这一问题,选取了早、中、晚3个时期的事故序列,对轴封破口发生时间做敏感性分析.结果表明,早期破口会加速严重事故的进程,而较晚时间发生破口,尤其是事故中期发生破口能较好地延缓压力容器损毁进程.相关数据可为有关人员防范和缓解严重事故提供参考.
Abstract:
Station blackout(SBO)is one of the important events in nuclear power plant(NNP)that can lead to serious consequence.We adopt the modular accident analysis program of CPR1000 to model and analyze the SBO accident.We analyzed the accident process of SBO accident for CPR1000 in detail by calculating parameters such as main circuit pressure,vessel water level,core tem-perature, and so on.The results show that SBO accident leads to vessel failure under high pressure,which causes the risk of containment direct heating.At the same time,large amounts of hydrogen is produced in the SBO accident.This part of hydrogen gradually migrates to the containment or auxiliary room,resulting in the risk of hydrogen explosion.As for the problem that the main pump is easy to break in SBO accident,we selected three periods of the accident sequence,the early period,middle period,and late period,to do the sensitivity analysis of time.The results show that seal loss-of-coolant accident(LOCA)in the early period accelerates the process of vessel failure,and in the later period and especially in the middle period,seal LOCA can delay the accident process.Data in this paper will provide a reference for relevant personnel for preventing and mitigating of serious accidents.

参考文献/References:

[1] 张亚培,田文喜,秋穗正,等.CPR1000全厂断电事故瞬态特性分析[J].原子能科学技术,2011,45(9):1056-1059.
[2] 李龙泽,王明军,田文喜,等.CPR1000全厂断电叠加蒸汽发生器安全阀误开启事故引起的严重事故分析[J].原子能科学技术,2014,48(6):1020-1025.
[3] TRIVEDI A K,ALLISON C,KHANNA A,et al.AP1000 station blackout study with and without depressurization using RELAP5/SCDAPSIM[J].Nuclear Engineering and Design,2016,307:299-308.
[4] LI G,LIU M,WANG J S,et al.MELCOR 2.1 analysis of melt behavior in a BWR lower head during LOCA and SBO accident[J].Annals of Nuclear Energy,2016,90:195-204.
[5] YIN S S,ZHANG Y P,TIAN W X,et al.Simulation of the small modular reactor severe accident scenario res-ponse to SBO using MELCOR code[J].Progress in Nuclear Energy,2016,86:87-96.
[6] 王珏,梁国兴.基于RELAP5与MELCOR联合分析方法的压水堆严重事故研究[J].核科学与工程,2016,36(2):223-230.
[7] LIN H T,WANG J R,HUANG K C,et al.Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE[J].Annals of Nuclear Energy,2016,89:1-18.
[8] GóMEZ-GARCíA-TORANO I,SáNCHEZ ESPINOZA V H,STIEGLITZ R.Investigation of SAM measures during selected MBLOCA sequences along with station blackout in a generic Konvoi PWR using ASTECV2.0[J].Annals of Nuclear Energy,2017,105:226-239.
[9] GóMEZ-GARCíA-TORANO I,SáNCHEZ ESPINOZA V H,STIEGLITZ R,et al.Assessment of primary and secondary bleed and feed procedures during a station blackout in a German Konvoi PWR using ASTECV2.0[J].Annals of Nuclear Energy,2018,113:476-492.
[10] ZUBAIR M,ABABNEH A,ISHAG A.Station black out concurrent with PORV failure using a generic pressurized water reactor simulator[J].Annals of Nuclear Energy,2017,110:1081-1090.
[11] PARK S,LEE J Y.A comparative study of station blackout scenario dynamics initiated by internal and seismic event in boiling water reactor[J].Annals of Nuclear Energy,2017,108:329-342.
[12] BAE B U,PARK Y S,KIM J R,et al. Integral effect test on station blackout(SBO)scenario with steam ge-nerator tube rupture(SGTR)in ATLAS facility[J].Nuclear Engineering and Design,2018,328:107-114.
[13] BAO H,ZHAO H H,ZHANG H B,et al.Safe reactor depressurization windows for BWR Mark I station black out accident management strategy[J]. Annals of Nuclear Energy,2018,114:518-529.
[14] 樊申.秦山核电厂全厂断电事故研究和厂外后果分析[D].北京:中国原子能科学研究院,2005.

备注/Memo

备注/Memo:
收稿日期:2018-03-13 录用日期:2018-05-02
基金项目:福建省科技厅计划项目(2016H0034)
*通信作者:hfmiao@xmu.edu.cn
引文格式:杨奥,黄志翱,缪惠芳,等.CPR1000全厂断电事故模拟及主泵轴封破口敏感性分析[J].厦门大学学报(自然科学版),2018,57(5):629-633.
Citation:YANG A,HUANG Z A,MIAO H F,et al.Simulation of station blackout accident for CPR1000 and sensitivity analysis of main pump seal loss-of-coolant accident[J].J Xiamen Univ Nat Sci,2018,57(5):629-633.(in Chinese)
更新日期/Last Update: 1900-01-01