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Experimental evaluation of re-entrainment from wet scrubber filtered containment venting systems

机译:湿式洗涤器过滤器储存通风系统重新夹具的实验评价

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Wet scrubber-based filtered containment venting systems (FCVSs) are commonly deployed at nuclear power plants, owing to the high degree of aerosol, iodine, and organic iodine retention that is possible through the pool scrubbing action that takes place during their operation. However, after a FCVS has been operating during a severe accident, the pool water will become extremely contaminated with previously-captured radionuclides, and the bubbling action of gases passing through the pool, could result in the re-entrainment of contaminated liquid droplets into the gas stream. This would produce a secondary source term during the late phases of an accident. As such, a set of experiments have been conducted in order to evaluate the aerosol re-entrainment rates and size distribution from a system prototypical of a pool-type FCVS. Entrainment rates were measured by tracking the carry-over of a NaCl tracer into a set of liquid traps, while the size of the re-entrained droplets was measured with a phase Doppler anemometer. The experiment employed a prototypical venturi nozzle and gas injection conditions to examine the influence of gas flow rate, liquid level, and pool water temperature. Entrainment factors between 5 x 10(-5) and 1 x 10(-3) were measured, and the water droplet count median diameters were between 3 and 13 mu m, and fairly wide particle size distributions, with mass mean diameters were on the order of 40-140 mu m. These experimental results help the assessment of the potential magnitude of the late phase source term hazards posed by the fission products retained in pool-type FCVS (secondary release), and the potential loading on the secondary dry filter stage (metal fiber filters) employed in FCVSs after the primary pool scrubbing stage. The secondary metal fiber filters should have a high efficiency in capturing water droplets produced through this mechanism, given the droplet's relatively large size.
机译:由于通过在其操作期间发生的池洗涤作用,可以在核电站核发生物,湿式洗涤器的过滤通风系统(FCVSS)通常在核发生物中展开。然而,在严重事故期间运行FCV后,泳池水将极度污染,以前捕获的放射性核素,并且通过游泳池的气体鼓泡作用可能导致将污染的液滴重新夹带到污染的液体液滴中气流。这将在发生事故的后期阶段产生二级来源。因此,已经进行了一组实验,以评估从池型FCV的系统原型的气溶胶再夹具速率和尺寸分布。通过将NaCl示踪剂的携带转移到一组液体阱中来测量夹带速率,而重新夹带液滴的尺寸用相多普勒风速计测量。实验采用原型文丘里管喷嘴和气体注入条件,以检查气体流速,液位和水池温度的影响。测量5×10( - 5)和1×10(-3)之间的夹带因子,水滴计数中值直径在3至13亩,并且相当宽的粒度分布,质量平均直径在40-140亩的顺序。这些实验结果有助于评估在池型FCVS(二次释放)中保留的裂变产物所带来的后期阶段源期危害的潜在幅度,以及所用的二次干滤波器级(金属纤维过滤器)上的潜在负载主要池擦洗阶段后的FCVSS。鉴于液滴相对较大的尺寸,二次金属纤维过滤器应具有高效率的捕获通过该机制产生的水滴。

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