An integral effect test for a MSLB （main stem line break） was performed with the ATLAS （advanced thermal-hydraulic test loop for accident simulation） by KAERI （Korea Atomic Energy Research Institute）. A MSLB is ...An integral effect test for a MSLB （main stem line break） was performed with the ATLAS （advanced thermal-hydraulic test loop for accident simulation） by KAERI （Korea Atomic Energy Research Institute）. A MSLB is defined as a pipe break in the main steam system. This data was used to validate the safety analysis code SPACE （safety and performance analysis code for nuclear power plants）. In the test, a double-ended guillotined break of the main steam line was simulated. After steady-state was reached, the test was started by opening the break simulation valves. With the start of the test, the pressure of the secondary system decreased rapidly, and reached the set-point of the LSGP （low steam generator pressure） signal. With the occurrence of the LSGP signal, the main steam isolation valves were closed. The SIPs （safety injection pumps） were started by the LPP （low pressurizer pressure） signal. In order to validate the SPACE code, a double-ended guillotine break of the main steam line at ATLAS was simulated. Most of the results show good agreement between the experiment data and the code calculated values.展开更多
The highest thermal-hydraulic pressure in the containment occurs when reactor coolant in the first loop and steam in the secondary loop discharge simultaneously,and when the maximum amount of energy from reactor unit ...The highest thermal-hydraulic pressure in the containment occurs when reactor coolant in the first loop and steam in the secondary loop discharge simultaneously,and when the maximum amount of energy from reactor unit enters to containment volume. In this paper, we investigate temperature and pressure variations in the VVER 1000 containment compartments owing to concurrent break in the pipelines of the primary and secondary loops. A two-phase, multicellular model is applied in the presence of non-condensable gases. Convection and conduction through the main heat structures inside the containment are also considered. The predicted results agree well with available data. Maximum values of pressure and temperature in the containment are then calculated and compared to the design values. If LOCA and MSLB occur simultaneously, the maximum pressure would exceed the design value and integrity of the containment would be threatened.展开更多
依托第三代核电机组华龙一号机组数据,对华龙一号机组热停堆工况下发生主蒸汽管线破口事故(Main Steam Line Break,MSLB)后的反应堆安全性进行了仿真分析,得到该故障工况下机组关键参数的瞬态特性。仿真结果表明:热停堆工况下,一回路硼...依托第三代核电机组华龙一号机组数据,对华龙一号机组热停堆工况下发生主蒸汽管线破口事故(Main Steam Line Break,MSLB)后的反应堆安全性进行了仿真分析,得到该故障工况下机组关键参数的瞬态特性。仿真结果表明:热停堆工况下,一回路硼浓度较低时,发生主蒸汽管线破口事故,同时具有最高负反应性的一组控制棒组件卡在完全抽出的位置,堆芯将可能重返临界,通过一系列主要反应堆保护动作及专设安全设施动作后,反应堆最终停堆。展开更多
利用核动力系统安全分析程序中的三维水力部件模型,模拟了CPR1000反应堆在发生主蒸汽管道破裂(main steam line break,MSLB)事故后,堆芯入口处的温度空间分布情况。分析了主蒸汽管道破裂事故发生后,堆芯入口处的流体温度分布形成原因。...利用核动力系统安全分析程序中的三维水力部件模型,模拟了CPR1000反应堆在发生主蒸汽管道破裂(main steam line break,MSLB)事故后,堆芯入口处的温度空间分布情况。分析了主蒸汽管道破裂事故发生后,堆芯入口处的流体温度分布形成原因。结果表明:单环路主蒸汽管道破裂后会导致堆芯入口温度分布不均匀,破口侧温度降低。展开更多
文摘An integral effect test for a MSLB （main stem line break） was performed with the ATLAS （advanced thermal-hydraulic test loop for accident simulation） by KAERI （Korea Atomic Energy Research Institute）. A MSLB is defined as a pipe break in the main steam system. This data was used to validate the safety analysis code SPACE （safety and performance analysis code for nuclear power plants）. In the test, a double-ended guillotined break of the main steam line was simulated. After steady-state was reached, the test was started by opening the break simulation valves. With the start of the test, the pressure of the secondary system decreased rapidly, and reached the set-point of the LSGP （low steam generator pressure） signal. With the occurrence of the LSGP signal, the main steam isolation valves were closed. The SIPs （safety injection pumps） were started by the LPP （low pressurizer pressure） signal. In order to validate the SPACE code, a double-ended guillotine break of the main steam line at ATLAS was simulated. Most of the results show good agreement between the experiment data and the code calculated values.
文摘The highest thermal-hydraulic pressure in the containment occurs when reactor coolant in the first loop and steam in the secondary loop discharge simultaneously,and when the maximum amount of energy from reactor unit enters to containment volume. In this paper, we investigate temperature and pressure variations in the VVER 1000 containment compartments owing to concurrent break in the pipelines of the primary and secondary loops. A two-phase, multicellular model is applied in the presence of non-condensable gases. Convection and conduction through the main heat structures inside the containment are also considered. The predicted results agree well with available data. Maximum values of pressure and temperature in the containment are then calculated and compared to the design values. If LOCA and MSLB occur simultaneously, the maximum pressure would exceed the design value and integrity of the containment would be threatened.
文摘依托第三代核电机组华龙一号机组数据,对华龙一号机组热停堆工况下发生主蒸汽管线破口事故(Main Steam Line Break,MSLB)后的反应堆安全性进行了仿真分析,得到该故障工况下机组关键参数的瞬态特性。仿真结果表明:热停堆工况下,一回路硼浓度较低时,发生主蒸汽管线破口事故,同时具有最高负反应性的一组控制棒组件卡在完全抽出的位置,堆芯将可能重返临界,通过一系列主要反应堆保护动作及专设安全设施动作后,反应堆最终停堆。
文摘利用核动力系统安全分析程序中的三维水力部件模型,模拟了CPR1000反应堆在发生主蒸汽管道破裂(main steam line break,MSLB)事故后,堆芯入口处的温度空间分布情况。分析了主蒸汽管道破裂事故发生后,堆芯入口处的流体温度分布形成原因。结果表明:单环路主蒸汽管道破裂后会导致堆芯入口温度分布不均匀,破口侧温度降低。
