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Effect of boric acid mass transfer on the accumulation thereof in a fuel core under emergency modes at NPPs with WMR

机译：带有WMR的核电厂在紧急模式下硼酸传质对其在燃料堆芯中积累的影响

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摘要

Boric acid mass transfer processes in the reactor facilities with WMR are considered for the case of an emergency with breaking of the main circulation pipeline (MCP) and the operation of the passive safety systems, such as first-, second-, and third-stage accumulator tank systems, and a passive heat removal system (PHRS). Calculation results are presented for a change in the boric acid concentration in the fuel core (FC) of a water-moderated reactor (WMR) in the case of an emergency process. The calculations have been performed for different values of drop entrainment of boric acid from the reactor (0, 0.2, 2%). A substantial excess of the maximum concentration of boric acid has been found to occur 24 hours after an emergency event with a break of MCP. It is shown that increasing the droplet entrainment of boric acid causes the crystallization and accumulation thereof in the FC to become slower. The mass of boric acid deposits on the elements of internals is determined depending on the values of drop entrainment. These results allow one to draw a conclusion concerning the possibility of accumulation and crystallization of boric acid in the FC, because the latter event could lead to a blocking of the flow cross section and disturbance in the heat removal from fuel elements. A review of available literature data concerning the thermal properties of boric acid solution (density, viscosity, thermal conductivity) is presented. It is found that the available data are of quite a general character, but it does not cover the entire range of parameters (temperature, pressure, acid concentrations) inherent in a possible emergency situation at nuclear power plants with WMR. It is demonstrated that experimental study of boric acid drop entrainment at the parameters inherent in the emergency mode of WMR operation, as well as the studies of boric acid thermal properties in a wide range of concentrations, are required.
机译：在发生紧急情况时，考虑到主循环管道（MCP）中断以及被动安全系统（例如第一，第二和第三阶段）的运行，考虑使用带有WMR的反应堆设施中的硼酸传质过程蓄能箱系统和被动排热系统（PHRS）。给出了在紧急情况下水调节反应堆（WMR）的燃料堆芯（FC）中硼酸浓度变化的计算结果。对于来自反应器的硼酸滴入夹带的不同值（0％，0.2％，2％），已经执行了计算。发现在发生MCP中断的紧急事件发生24小时后，硼酸的最大浓度大大过量。已显示出增加硼酸的液滴夹带导致其结晶和在FC中的积累变慢。硼酸沉积在内部元件上的质量取决于液滴夹带的值。这些结果使人们可以得出有关硼酸在FC中积累和结晶的可能性的结论，因为后一种情况可能会导致流动横截面的阻塞和从燃料元件中除热的干扰。本文介绍了有关硼酸溶液热性质（密度，粘度，导热系数）的现有文献数据。已经发现，可用数据具有相当普遍的特征，但是它并未涵盖具有WMR的核电厂可能发生紧急情况时固有的整个参数范围（温度，压力，酸浓度）。结果表明，需要在WMR紧急操作模式下固有的参数下进行硼酸液滴夹带的实验研究，以及在宽浓度范围内进行硼酸热性质的研究。

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  • 来源
    《Thermal engineering》 |2017年第7期|490-495|共6页
  • 作者

    Morozov A. V.; Sorokin A. P.; Ragulin Sergei V.; Pityk Anna V.; Sahipgareev A. R.; Soshkina Aleksandra S.; Shlepkin A. S.;

  • 作者单位

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

    State Scientific Research Center, Leypunsky Institute for Physics and Power Engineering, Obninsk, Kaluga oblast, Russian Federation;

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  • 关键词

    accumulation; boric acid; droplet entrainment; emergency mode; fuel core cooling; WMR;

    机译：积累;硼酸液滴夹带;紧急模式;燃料芯冷却;WMR;

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