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Accident Analysis of Fukushima Daiichi Nuclear Power Plant Unit 2 by the SAMPSON Severe Accident Code

机译:根据SAMPSON严重事故代码对福岛第一核电站2号机组进行事故分析

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The transient process of the accident at the Fukushima Daiichi Nuclear Power Plant Unit 2 was analyzed by the severe accident analysis code, SAMPSON. One of the characteristic phenomena in Unit 2 is that the reactor core isolation cooling system (RCIC) worked for an unexpectedly long time (about 70 h) without batteries and consequently core damage was delayed when compared to Units 1 and 3. The mechanism of how the RCIC worked such a long time is thought to be due to balance between injected water from the RCIC pump and the supplied mixture of steam and water sent to the RCIC turbine. To confirm the RCIC working conditions and reproduce the measured plant properties, such as pressure and water level in the pressure vessel, we introduced a two-phase turbine driven pump model into SAMPSON. In the model, mass flow rate of water injected by the RCIC was calculated through turbine efficiency degradation the originated from the mixture of steam and water flowing to the RCIC turbine. To reproduce the drywell pressure, we assumed that the torus room was flooded by the tsunami and heat was removed from the suppression chamber to the sea water. Although uncertainties, mainly regarding behavior of debris, still remain because of unknown boundary conditions, such as alternative water injection by fire trucks, simulation results by SAMPSON agreed well with the measured values for several days after the scram.
机译:福岛第一核电站2号机组的事故瞬态过程已通过严重事故分析代码SAMPSON进行了分析。第2单元中的特征现象之一是,反应堆堆芯隔离冷却系统(RCIC)在没有电池的情况下工作了意想不到的长时间(约70小时),因此与第1单元和第3单元相比,堆芯的损坏被延迟了。 RCIC如此长时间的工作被认为是由于RCIC泵注入的水与送入RCIC涡轮机的蒸汽和水的混合物之间的平衡。为了确认RCIC的工作条件并重现测得的设备特性(例如压力容器中的压力和水位),我们在SAMPSON中引入了两相涡轮驱动泵模型。在该模型中,由RCIC注入的水的质量流量是通过涡轮效率降低而计算出来的,该效率降低是由流入RCIC涡轮的蒸汽和水的混合物引起的。为了重现干井压力,我们假设环岛房间被海啸淹没,热量从抑制室被带走到海水中。尽管由于不确定的边界条件(例如消防车注水)仍存在主要关于碎片行为的不确定性,但SAMPSON的模拟结果与Scram之后几天的测量值非常吻合。

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