魏承君, 于倩, 杨安霞, 隋丹婷, 孟琳, 黄俊文. AP1000常规岛第一跨厂房内主给水管道破裂事故瞬态泄放特性分析[J]. 核科学与工程, 2022, 42(4): 905-915.
引用本文: 魏承君, 于倩, 杨安霞, 隋丹婷, 孟琳, 黄俊文. AP1000常规岛第一跨厂房内主给水管道破裂事故瞬态泄放特性分析[J]. 核科学与工程, 2022, 42(4): 905-915.
WEI Chengjun, YU Qian, YANG Anxia, SUI Danting, MENG Lin, HUANG Junwen. Analysis on Transient Discharge Characteristics of the Main Feed Water Pipeline Break Accident in the First Span Plant of the AP1000 Conventional Island[J]. Chinese Journal of Nuclear Science and Engineering, 2022, 42(4): 905-915.
Citation: WEI Chengjun, YU Qian, YANG Anxia, SUI Danting, MENG Lin, HUANG Junwen. Analysis on Transient Discharge Characteristics of the Main Feed Water Pipeline Break Accident in the First Span Plant of the AP1000 Conventional Island[J]. Chinese Journal of Nuclear Science and Engineering, 2022, 42(4): 905-915.

AP1000常规岛第一跨厂房内主给水管道破裂事故瞬态泄放特性分析

Analysis on Transient Discharge Characteristics of the Main Feed Water Pipeline Break Accident in the First Span Plant of the AP1000 Conventional Island

  • 摘要: 常规岛厂房第一跨是AP/CAP系列核电机组所特有的结构设计,位于核岛厂房与常规岛厂房之间,布置有执行纵深防御功能的设备冷却水泵、变频装置(variable-frequency drive,VDF)、蓄电池室等核岛相关设备。主给水管道破裂(MFLB)事故中破口处最大泄放水量及最大瞬时泄放量与破口尺寸以及主给水泵(MFWP)停泵时间相关,需要对主给水管道破裂事故进行保守工况的确定,为纵深防御设备的布置提供指导策略。本文根据四种不同的主给水泵停泵逻辑选取了四种典型的破口尺寸,基于完整的二回路热力系统模型,针对四种破口尺寸进行建模分析并得到了不同事故序列以及四种工况下的动态泄放曲线。按照核岛要求的边界条件及足够保守的假设下,当主给水管道破裂后,破口尺寸Ⅱ事故工况下总泄放水量最大,破口尺寸Ⅳ事故工况下破口的瞬时泄放量最大。

     

    Abstract: The first span of the conventional island plant is a unique structural design of AP/CAP series nuclear power plants, which is located between the nuclear island and the conventional island. It is equipped with the equipment cooling water pump, variable-frequency drive, battery room and other nuclear island-related equipment. In the main water supply pipeline rupture accident, the total maximum discharge amount and the maximum instantaneous discharge amount in the MFLB are related to the break size and the trigger time of the main feed water pump(MFWP). Therefore, it is necessary to confirm the conservative working condition of the MFLB accident, so as to provide guidance strategy for the layout of depth defense equipment. In this paper, four typical break sizes are selected according to the trigger logic of four different main feed water pumps. Based on the complete model of the secondary circuit thermal system, modeling and analysis of four kinds of break sizes are carried out, and different accident sequences and dynamic discharge curves under four working conditions are obtained. According to the boundary conditions required by the nuclear island and sufficient conservative assumptions, when the main feed water pipeline breaks down, the total discharge amount of the break size Ⅱ is the largest under the accident condition and the instantaneous discharge amount of the break size Ⅳ is the largest under the accident condition.

     

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