2020 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[2K09-13] Molten Core Behavior, Mitigation of FCI/MCCI

Thu. Sep 17, 2020 3:40 PM - 5:05 PM Room K (Zoom room 11)

Chair:Kenji Kamiyama(JAEA)

4:10 PM - 4:25 PM

[2K11] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(7)Spreading experiment of molten core with sacrificial material

*Hiroshi Goda1, Satoru Kamohara1, Junichi Takeuchi1, Taro Toda1 (1. Mitsubishi Heavy Industries)

Keywords:Severe accident, Molten corium, MCCI, Spreading experiment

In order to develop a new sacrificial material that improves the coolability of molten corium during severe accident, as well as to develop an evaluation model for predicting the corium spreading behaviour, spreading experiment of molten corium with sacrificial material has been performed. This spreading experiment involves two different materials for the substrate, i.e. concrete with sacrificial material and ceramic zirconia. Different spreading behaviours for these two substrate materials have been observed, and accordingly it has been confirmed that it is effective to apply the sacrificial material for improving corium spreading. Obtained data are utilised for validating the new physical model for evaluating the corium spreading behaviour.