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上海核工程研究设计院 上海 200233
Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
王伟伟,男,1985年出生,2013年于西安交通大学获博士学位,研究领域为非能动核电厂大破口失水事故和长期冷却分析
收稿日期:2015-10-14,
录用日期:2015-12-14,
纸质出版日期:2016-01-25
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王伟伟, 曹克美, 戚展飞. GSI-191问题喷射冲击影响区域的计算分析[J]. 核技术, 2016,39(2):020604
Weiwei WANG, Kemei CAO, Zhanfei QI. Calculation and analysis of jet-impact influence zone in GSI-191 issue[J]. Nuclear techniques, 2016, 39(2): 020604
王伟伟, 曹克美, 戚展飞. GSI-191问题喷射冲击影响区域的计算分析[J]. 核技术, 2016,39(2):020604 DOI: 10.11889/j.0253-3219.2016.hjs.39.020604.
Weiwei WANG, Kemei CAO, Zhanfei QI. Calculation and analysis of jet-impact influence zone in GSI-191 issue[J]. Nuclear techniques, 2016, 39(2): 020604 DOI: 10.11889/j.0253-3219.2016.hjs.39.020604.
在压水堆LOCA (Loss of Coolant Accident)事故之后
高能管道流体喷射冲击导致破口附近的保温层等材料破裂为碎片。这些碎片随流体在安全壳内传输并在地坑滤网沉积形成碎片床
阻碍应急堆芯冷却系统的正常运行。部分碎片可能旁通滤网进入反应堆压力容器
从而引起一系列的效应。该问题被称之为GSI-191(GenericSafety Issue-191)问题。为解决GSI-191问题
首先需要确定破口附近产生的碎片量。当前研究基于ANSI/ANS58.2-1988标准和等效体积球体模型
自主开发了喷射冲击影响区域计算工具JETZOI。采用该工具计算获得的NEI (Nuclear Energy Institute)算例的喷射轮廓和等压线与美国核管会(United States Nuclear RegulatoryCommission
U.S NRC)的结果符合很好
从而实现了对NEI算例的成功复现。进一步进行了不同滞止工况的敏感性分析。分析结果表明
在相同的滞止压力下
流体温度的升高将导致影响区域破坏半径的减小和碎片量的减少。因此在开展喷射冲击试验获得影响区域的破坏半径时
应当保守选取冷段双端断裂作为极限工况以使喷射冲击产生的碎片量最大。
Background:
2
In Loss of Coolant Accidents (LOCAs)
jet impact of fluid from a high energy pipe could damage insulation materials
etc. near the break into debris
which would be transported along with fluid in containment and finally deposit on sump screen to form a debris bed
impeding normal operation of Emergency Core Cooling System (ECCS). A part of the debris may bypass the screen and flow into the reactor pressure vessel
resulting in a series of effects. The issue is referred as GSI-191 (Generic Safety Issue 191) problem.
Purpose:
2
In order to solve this issue
quantity of debris generated near the break should be determined firstly.
Methods:
2
One calculation tool for jet impact Zone of Influence (ZOI) was developed independently based on ANSI/ANS 58.2-1988 standard and equivalent volume sphere model.
Results:
2
The jet outline and isobar of the Nuclear Energy Institute (NEI) test case obtain
ed by the tool agreed well with the results of U.S NRC (United States Nuclear Regulatory Commission) and thus the duplication of the NEI test case was realized successfully. Furthermore
sensitivity analysis under different stagnation conditions was performed. Analysis results showed that
under the same stagnation pressure
increase of fluid temperature will result in the decrease of the ZOI destruction radius and debris quantity.
Conclusion:
2
So when jet impact test is performed to obtain the ZOI destruction radius
double ended guillotine break of cold leg should be selected conservatively as the limiting condition to maximum the debris quantity generated during jet impact process.
李 焕荣 , 王 鹏 , 李 达然 , . AP1000 核电站常规岛高能管道断裂分析 . 电力建设 , 2011 . 32 ( 3 ): 88 - 91 .
LI Huanrong , WANG Peng , LI Daran , . Analysis on high-energy pipe rupture in conventional island of AP1000 nuclear power plant . Electric Power Construction , 2011 . 32 ( 3 ): 88 - 91 .
American Nuclear Society (ANS) . American national standard design basis for protection of light water nuclear power plants against the effects of postulated pipe rupture . ANSI/ANS , 1988 .
. Knowledge base for the effect of debris on pressurized water reactor emergency core cooling sump performance . NUREG/CR-6808, Los Alamos National Laboratory , 2003 .
Nuclear Energy Institute (NEI) . Pressurized water reactor sump performance evaluation methodology . 2004 . 1 .
U.S. NRC . Safety evaluation by the office of nuclear reactor regulation related to NRC generic letter 2004-02 . NEI , 2004 . 2 .
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