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首页> 外文期刊>Thermal engineering >Estimation of Thermal Loads on the WER Vessel under Conditions of Inversion of the Stratified Molten Pool in a Severe Accident
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Estimation of Thermal Loads on the WER Vessel under Conditions of Inversion of the Stratified Molten Pool in a Severe Accident

机译：严重事故中分层熔池倒置条件下WER容器上的热负荷估算

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Analysis of the thermal state of molten pools that can be formed on the vessel bottom of the WER-600 medium-power reactor during a severe anticipated accident with melting of the core is represented. Two types of the molten pool of core materials, with the two-layer and inverse three-layer stratification, are considered. Thermal loads acting on the reactor vessel from the melt are estimated depending on its formation time. Features of the thermal state of the melt in the case of its inverse stratification are analyzed. It is shown that thermal loads on the reactor vessel exceed the critical heat flux (CHF) when forming the two-layer stratified molten pool 10 and 24 h after its shutdown, and the thermal load is close to the corresponding CHF or somewhat exceeds it in 72 h. In the case of the formation of the inverse structure of the melt, one can observe a decrease by more than 2.5 times (in comparison with the two-layer stratified structure) in the thermal load on the reactor vessel in the region of its contact with the upper layer of the steel melt. Analysis of results showed that maximum densities of heat flux to the reactor vessel from the bottom metallic layer with the melt inversion did not exceed corresponding CHFs 24 and 72 h after the reactor shutdown. Because the thermal load on the reactor vessel can be localized in the region of its bottom, where the CHF is relatively small, during the inverse stratification of the melt, there is a need to carry out further in-depth experimental and analytical investigations of conditions for formation of the stratified molten pool and to obtain corrected experimental CHFs for conditions and outlines of cooling the external surface of the WER-600 vessel in a severe accident.
机译：表示了在严重的预料中的事故（伴随堆芯熔化）期间，在WER-600中功率反应堆的容器底部可能形成的熔池热状态的分析。考虑了两类芯材料的熔池，具有两层和逆三层分层。取决于熔体的形成时间，估计其从熔体作用到反应器容器上的热负荷。分析了熔体逆分层情况下的热态特征。结果表明，在形成两层分层熔池后的10和24小时内，反应堆容器上的热负荷超过了临界热通量（CHF），并且热负荷接近相应的CHF或略大于它。 72小时在形成熔体的逆结构的情况下，可以观察到在与容器接触的区域中反应堆容器的热负荷降低了2.5倍以上（与两层分层结构相比）。钢熔体的上层。结果分析表明，在反应堆停工后的24 h和72 h，从底部金属层到具有熔融倒相的反应堆容器的最大热通量密度不超过相应的CHF。由于反应堆容器上的热负荷可位于其底部的CHF相对较小的区域，因此在熔体逆分层过程中，需要对条件进行进一步的深入实验和分析研究用于形成分层熔池并获得针对严重事故中冷却WER-600容器外表面的条件和轮廓的校正实验CHF。

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