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EXPERIMENTAL INVESTIGATION ON BOILING FLOW CHARACTERISTICS UNDER PASSIVE IVR-ERVC CONDITIONS

机译:被动IVR-ERVC条件下沸腾流动特性的实验研究

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In vessel retention (IVR) of molten core debris via water cooling at the external surface of the reactor vessel is an important severe accident management feature of advanced passive plants. During postulated severe accidents, the heat generated due to the molten debris relocation to the lower reactor pressure vessel head needs to be removed continuously to prevent vessel failure. Besides the local critical heat flux (CHF) of outer wall surface which is the first importance, a stable feature of natural circulation flow and an effective natural circulation capability within the external reactor vessel cooling (ERVC) channel tend to be rather crucial for the success of IVR. Under this circumstance, a full-height ERVC test infrastructure for large advanced pressurized water reactor (PWR) IVR strategy engineering validation, namely reactor pressure vessel external cooling Ⅱ test facility (REPEC-II), has been designed and constructed in Shanghai Jiao Tong University (SJTU). And therefore, a brief introduction to the SJTU REPEC Ⅱ facility as well as the experimental progress to date, is hereby given in the paper. During test campaign on the REPEC Ⅱ facility, the one-dimensional natural circulation boiling flow characteristics during IVR-ERVC severe accident mitigation are investigated, with the experimental observation and measurement on natural circulation flow characteristics within the REPEC Ⅱ test facility. Based on the abundant results acquired in the test campaign, it is attempted, in this paper, to summarize and evaluate the ERVC performances and trends under various practical engineered conditions. The main evaluation results includes: influence on ERVC flow characteristics of various non-uniform heat load distribution cooling limits, the observed sinusoidal oscillation is suggested to be flashing-induced density wave oscillations and the oscillation period correlated well with the passing time of single-phase liquid in the riser. It is expected that these conclusions may help designers to have a reliable estimate of the impact of some related engineered factors on real IVR-ERVC performance. In vessel retention; external reactor vessel cooling; critical heat flux; natural circulation; oscillations.
机译:通过水冷却在反应堆容器外表面的熔融堆芯碎屑在容器中的滞留(IVR)是高级被动设备的重要严重事故管理特征。在假定的严重事故中,由于熔融碎屑移至较低反应堆压力容器顶部而产生的热量需要连续清除,以防止容器故障。除了最重要的是外壁表面的局部临界热通量(CHF)之外,反应堆外部容器冷却(ERVC)通道内自然循环流的稳定特征和有效自然循环能力对成功至关重要。 IVR。在这种情况下,已经在上海交通大学设计建造了用于大型先进压水堆(PWR)IVR战略工程验证的全高ERVC测试基础设施,即反应堆压力容器外部冷却Ⅱ测试设施(REPEC-II)。 (上海交通大学)。因此,本文简要介绍了SJTU REPECⅡ设备以及迄今为止的实验进展。在REPECⅡ设施的测试活动中,研究了IVR-ERVC减轻严重事故时的一维自然循环沸腾流动特性,并通过对REPECⅡ测试设施内的自然循环流动特性进行了实验观察和测量。基于在测试活动中获得的丰富结果,本文试图总结和评估ERVC在各种实际工程条件下的性能和趋势。主要评估结果包括:对各种非均匀热负荷分布冷却极限的ERVC流动特性的影响,建议观察到的正弦振荡是由闪烁引起的密度波振荡,并且振荡周期与单相的通过时间密切相关。提升管中的液体。可以预期,这些结论可以帮助设计人员可靠地估计一些相关工程因素对实际IVR-ERVC性能的影响。在容器中;外部反应堆容器冷却;临界热通量;自然循环振荡。

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