In-Vessel Retention (IVR) strategy with in-vessel water injection could mitigate the thermal focusing effect of the light metallic layer, and reduce the possibility of vessel failure and the release of fission products. Water injection on the molten Zirconium-Stainless steel metallic pool experiment (ATOM) has been performed to investigate the effect of water injection on the heat transfer of the molten pool. After water injection, a film boiling is formed on the top of the molten pool. With Taylor instability, a simplified model is used to derive the form of the film boiling. By fitting it with the ATOM experiment data, a new correlation of water injection on the prototype material for the possible stratified layer molten pool is obtained. The ATOM correlation could predict the experimental results well. The maximum relative error for the ATOM experiment is 28.5%, for the ELIAS experiment is 77.3%, and for the ANAIS experiment is 15.0%. By applicating the ATOM correlation of the heat transfer coefficient as a function of surface temperature to the reactor case, it is found that the vessel failure might not occur with the large aspect ratio (H/D) in the light metallic layer and with the top boundary condition of a water layer.

容器内注水的容器内滞留 (IVR) 策略可以减轻轻金属层的热聚焦效应，减少容器失效和裂变产物释放的可能性。已经进行了对熔融锆不锈钢金属池实验 (ATOM) 的注水，以研究注水对熔池传热的影响。注水后，在熔池顶部形成薄膜沸腾。对于泰勒不稳定性，使用简化模型来推导薄膜沸腾的形式。通过将其与 ATOM 实验数据拟合，获得了可能分层熔池的原型材料上注水的新关联。ATOM相关性可以很好地预测实验结果。ATOM 实验的最大相对误差为 28.5%，ELIAS 实验的最大相对误差为 77.3%，ANAIS 实验的最大相对误差为 15.0%。通过将作为表面温度函数的传热系数的 ATOM 相关性应用于反应器外壳，发现大纵横比可能不会发生容器故障（H / D ) 在轻金属层和水层的顶部边界条件。