高浓度蒸汽产生条件下铈射流破裂的三维 cfd 模拟

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-07-14 DOI:10.1016/j.net.2024.07.034
Jeong-Hyun Eom, Ji-Won Choi, Gi-Young Tak, In-Sik Ra, Huu Tiep Nguyen, Hae-Yong Jeong
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引用次数: 0

摘要

由于严重事故期间舱外现象的复杂性,以往的 CFD 应用大多仅限于流体力学方面。本研究使用 STAR-CCM + 代码对高强度蒸汽产生下的射流破裂和碎片床形成进行了数值分析。对 MATE06 实验的 CFD 预测显示了与实验结果一致的射流破裂发展模式。预测的射流破裂长度与 MATE06 早期的数据十分吻合。然而,在后期阶段,MATE 06 和模拟预测的前缘位置存在一些差异。这归因于一些碎裂段与喷流柱的分离和重新连接的非周期性重复。实验与 CFD 模拟之间摩擦力或剪应力的差异也会导致蒸汽产生量的不确定性。总之,本研究对于成功模拟高强度蒸汽产生条件下的一系列射流破裂过程和碎片床的形成具有重要意义。在今后的研究中,需要通过更多的实验评估来升级当前的模型,并开发出更复杂的模型,以提供更逼真的舱外现象模拟。
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A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition
The complexity of ex-vessel phenomena during a severe accident limits the most previous CFD applications only to hydrodynamic aspects. The present study performs numerical analysis of jet breakup and debris bed formation under intensive steam generation using the STAR-CCM + code. The CFD prediction of the MATE06 experiment demonstrates jet breakup progression patterns consistent to the experiment results. The predicted jet breakup lengths are in good agreement with the MATE 06 data in earlier stage. However, some disparities of the leading-edge position between the MATE 06 and the simulation are predicted in late stage. This is attributed to non-periodic repetitions of the detachment and reattachment of some fragmented segments to the jet column. The difference of frictional force or shear stress between the experiment and CFD simulation also causes uncertainty in the amount of steam generation. In overall, the present study becomes significant to simulate successfully the series of jet breakup process and debris bed formation under intensive steam generation condition. In future studies, it is required to upgrade the current model through more evaluation of experiments and to develop much sophisticated models which provide an enhanced realistic simulation of ex-vessel phenomena.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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