In future Light Water Reactors (LWR) containment failure should be prevented even for very unlikely core meltdown sequences with reactor pressure vessel (RPV) failure. In the case of such a postulated core meltdown accident in a future LWR the ex-vessel melt shall be retained and cooled in a special compartment inside the containment to exclude significant radioactive release to the environment. In such a case, a gate has to be designed to allow the melt release from the reactor cavity into the compartment. A series of transient experiments has been performed to investigate the melt gate ablation using iron and alumina melts as a simulant for the corium melt. The results of the KAPOOL tests are analyzed with the HEATING5 code in order to evaluate realistic cases of internally heated corium melts and melt gates with the same theoretical tool.
- Nuclear Engineering Division
Investigations on the Melt Gate Ablation by Ex-Vessel Core Melts in the KAPOOL Experiments
Eppinger, B, Schmidt-Stiefel, S, & Tromm, W. "Investigations on the Melt Gate Ablation by Ex-Vessel Core Melts in the KAPOOL Experiments." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 139-146. ASME. https://doi.org/10.1115/ICONE10-22120
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