首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >INVESTIGATION OF THE RELEASE OF ZINC IN THE REACTOR SUMP AND THE BEHAVIOR OF DISSOLVED ZINC AT HOTSPOTS IN THE REACTOR CORE AFTER A LOSS OF COOLANT ACCIDENT
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INVESTIGATION OF THE RELEASE OF ZINC IN THE REACTOR SUMP AND THE BEHAVIOR OF DISSOLVED ZINC AT HOTSPOTS IN THE REACTOR CORE AFTER A LOSS OF COOLANT ACCIDENT

机译:反应器顶峰中锌释放的调查以及冷却剂损失后反应器核心中火星上溶解锌的行为

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Generic experimental and methodical investigations were carried out aiming at the systematic elucidation of physico-chemical mechanisms and their influence on thermo-hydraulic processes, which can occur during the sump circulation operation after a loss-of-coolant accident (LOCA) in PWR. In such a case, borated coolant with dissolved zinc, formed by corrosion of zinc-coated containment installations, may reach core regions of higher temperature (hot spots). Experimental studies were done at semi-technical scale focused on the influence of such zinc-containing coolants on thermo-hydraulics at heating configurations similar to those inside the PWR core. The impact of physico-chemical mechanisms on thermo-fluid-dynamical behavior of coolant inside a 3×3 configuration of heating rods, which act as fuel rod simulators with spacer segments, was determined. As a test parameter, borated coolant with dissolved zinc was used with an initial fluid temperature in the range of 45...50°C. The initial boric acid concentration in the experiments is based on the accident scenario in german PWR. In the case of a LOCA, emergency cooling water (containing 2,500 ppm boron) from two refueling water storage tanks is injected into the primary cooling circuit during LOCA. During heat-up of zinc-containing coolant in a circuit, an increasing turbidity of the coolant fluid caused by forming colloids was observed first. This was followed by the formation of solid corrosion products consisting of zinc borates (identified by means of Raman spectroscopy [2]). In dependence of the temperatures of fluid and heatable surfaces, the solids showed various attributes concerning their mobilization potential, their density and their ability to form deposit layers. Deposits occurred at the rod surfaces as well as at the spacer segments. They effected a hindered heat transfer from the rod surfaces to the fluid, an increasing head loss at the spacers and some changes of the flow distribution. In addition, quantifications of the formed solid corrosion products including a characterization of released solid particles were done by means of microscope and particle analyzer. Subsequently, investigations were expanded considering original zinc sources (zinc-coated gratings) and a 16×16 shortened PWR fuel assembly dummy with a centered 8×8 heating rod configuration. Achieved experimental results allow conclusions about the solubility behavior of zinc corrosion products in borated coolant as well as about the formation of solids and the consequences thereof. Beside processes of deposit layer formation and particle release, further effects like outgassing of dissolved air and local subcooled boiling phenomena were observed, which can accelerate the remobilization of formed solids and may strengthen the mentioned mechanisms.
机译:进行了一般性的实验和方法研究,旨在系统地阐明理化机理及其对热-水力过程的影响,这可能会在压水堆失水事故(LOCA)后的集水槽循环运行期间发生。在这种情况下,由溶解锌的硼酸盐冷却剂(通过镀锌的安全壳设施的腐蚀而形成)可能会到达温度较高的核心区域(热点)。在半技术规模上进行了实验研究,重点是在类似于PWR堆芯内部的加热配置下,此类含锌冷却液对热工液压油的影响。确定了物理化学机制对加热棒3×3配置内的冷却剂的热流体动力学行为的影响,加热棒充当带有间隔段的燃料棒模拟器。作为测试参数,使用溶解锌的硼酸化冷却剂,其初始流体温度在45 ... 50°C范围内。实验中的初始硼酸浓度基于德国压水堆的事故情况。对于LOCA,在LOCA期间,将来自两个加油水储罐的应急冷却水(包含2500 ppm的硼)注入到主冷却回路中。在加热回路中的含锌冷却液时,首先观察到由于形成胶体而导致冷却液的浊度增加。随后形成由硼酸锌组成的固体腐蚀产物(通过拉曼光谱法确定[2])。取决于流体和可加热表面的温度,固体表现出各种有关其动员潜力,密度和形成沉积层的能力的属性。在杆表面以及间隔段上都出现了沉积物。它们阻碍了从杆表面到流体的热传递,增加了垫片上的压头损失,并改变了流量分布。另外,借助于显微镜和颗粒分析仪对形成的固体腐蚀产物进行定量,包括对释放的固体颗粒进行表征。随后,扩大了研究范围,考虑了原始的锌源(镀锌的格栅)和带有中心8×8加热棒结构的16×16缩短的PWR燃料组件假人。获得的实验结果可以得出有关硼腐蚀冷却剂中锌腐蚀产物的溶解行为以及固体形成及其后果的结论。除了沉积层形成和颗粒释放的过程外,还观察到了进一步的影响,例如溶解空气的脱气和局部过冷沸腾现象,这些现象可以加速形成的固体的迁移,并可能增强上述机制。

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