Steam Condensation Induced Water Hammer Simulations for Different Pipelines in Nuclear Reactor
We investigate steam condensation induced water hammer (CIWH) phenomena and present theoretical results for different kind of pipelines. We analyze the process with the WAHA3 model based on two-phase flow six first-order partial differential equations that present one dimensional, surface averaged mass, momentum and energy balances. A second order accurate high-resolution shock-capturing numerical scheme was applied with different kind of limiters in the numerical calculations. The applied two-fluid model shows some similarities to RELAP5 which is widely used in the nuclear industry to simulate nuclear power plant accidents. Experiments are planned for these geometries and will be performed in the PMK-2 facility, which is a full-pressure thermohydraulic model of the nuclear power plant of VVER-440/312 type and located in the Atomic Energy Research Institute Budapest, Hungary. Our recent calculation clearly shows that the six conditions of Griffith are only necessary conditions for CIWH but not sufficient, therefore further analysis are required before planning and building of nuclear reactors.
Steam condensation induced water hammer(CIWH) two-phase flow
Barna I. F Varga L (E)zs(o)l Gy
KFKI Atomic Energy Research Institut(AEKI) of the Hungarian Academy of Sciences, Thermo-hydraulic De KFKI Atomic Energy Research Institut(AEKI) of the Hungarian Academy of Sciences, Thermo-hydraulic De
国际会议
上海
英文
1434-1444
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）