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Numerical modeling on the discharged fluid flow from a glass melter by a Lagrangian approach

机译:用拉格朗日方法对玻璃熔炉排出的流体进行数值模拟

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摘要

In Japan, it is planned to use vitrification to immobilize high level radioactive liquid waste (HLLW) obtained from the nuclear reprocessing process. In the vitrification process, the HLLW will be mixed with molten glass in a joule-heated glass melter. The molten glass is then poured into a canister through a nozzle at the bottom of the melter. When some abnormalities occurred, feature of the discharged flow become different from that in normal conditions. We cannot observe the state of the molten glass inside the melter directly because of the severe environment. Accordingly, we cannot investigate the cause when the abnormalities occurred. Hence, numerical simulation of the discharged flow becomes important to understand and recover from operational problems or abnormalities with the glass melter. However, existing numerical models of the glass melter do not really simulate the discharged glass flow. In the present study, we introduce a new algorithm into an existing Lagrangian approach to efficiently simulate the discharged glass flow. To verify the model, 3D simulations were performed on a real scale system and got compared with the results of experimental validation tests. The simulation results show good agreement with the experimental results. Consequently, the new Lagrangian approach accurately simulates the molten glass flow.
机译:在日本,计划利用玻璃化来固定从核后处理过程中获得的高放射性废液(HLLW)。在玻璃化过程中,HLLW将在焦耳加热的玻璃熔炉中与熔融玻璃混合。然后将熔融玻璃通过熔化器底部的喷嘴倒入罐中。当发生某些异常时,排出流量的特性会与正常情况下有所不同。由于恶劣的环境,我们无法直接观察熔化器内部的熔融玻璃状态。因此,我们无法调查发生异常的原因。因此,对排出的流量进行数值模拟对于了解玻璃熔化器的运行问题或异常并从中恢复是很重要的。但是,玻璃熔炉的现有数值模型并不能真正模拟排出的玻璃流量。在本研究中,我们将一种新算法引入现有的拉格朗日方法中,以有效地模拟排出的玻璃流。为了验证模型,在真实规模的系统上进行了3D仿真,并将其与实验验证测试的结果进行了比较。仿真结果与实验结果吻合良好。因此,新的拉格朗日方法可以精确地模拟熔融玻璃的流动。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第7期|p.14-21|共8页
  • 作者单位

    Department of Systems Innovation, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656, Japan;

    Department of Systems Innovation, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656, Japan;

    Department of Systems Innovation, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656, Japan;

    Nuclear Fuel Cycle System Department, Nuclear Power Operations, IHI Co., Ltd., 1, Shin-nakahara-cho, lsogo-ku, Yokohama, Kanagawa 235-8501, Japan;

    Nuclear Fuel Cycle System Department, Nuclear Power Operations, IHI Co., Ltd., 1, Shin-nakahara-cho, lsogo-ku, Yokohama, Kanagawa 235-8501, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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