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.
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 .