TY - GEN
T1 - A new insight into molten corium concrete interaction with concrete ablation analysis for mitigation scheme
AU - Khurshid, Ilyas
AU - Alade, Amidu Muritala
AU - Addad, Yacine
AU - Afgan, Imran
N1 - Funding Information:
The authors wish to acknowledge Khalifa University of Science and Technology for funding this research. This publication is based upon work supported by the Khalifa University of Science and Technology under Award No. [8474000240]. We appreciate Farmer M.T of the Argonne National Laboratory for his support in developing model with CORQUNECH.
Publisher Copyright:
© 2021 American Society of Mechanical Engineers (ASME). All rights reserved.
PY - 2021
Y1 - 2021
N2 - The study presents the use of CORQUENCH simulator to simultaneously model the molten corium, composition of concrete, molten corium heat transfer models and solve the related chemical reactions. Using this modeling technique, the chemical reaction capabilities of CORQUENCH were successfully utilized which enabled the modeling of interaction between molten corium and concrete. The developed model was validated against experimental data and the results showed that the temperature of corium, composition of concrete and water injection time have a pronounced effect on mitigating depth of ablation and reactor integrity in case of a nuclear accident. In addition, the composition of concrete is the main controlling factor to mitigate ablation in the investigated case study. An alternative to concrete, could be a certain igneous rock (tested in this study), can lead to comparatively low rates of ablation due to its high thermal resistant properties. Furthermore, the injection of water (as a cooling agent) into the reactor cavity should also be optimized to enhance corium quenching to avoid ablation via basement meltthrough. As a consequence of concrete ablation by molten corium, the depth of ablation is expected to decrease to zero ablation with the suggested material in the selected case study. The concrete ablation mechanisms during MCCI are very case-dependent on the concrete solidus, liquidus and ablation temperature, respectively.
AB - The study presents the use of CORQUENCH simulator to simultaneously model the molten corium, composition of concrete, molten corium heat transfer models and solve the related chemical reactions. Using this modeling technique, the chemical reaction capabilities of CORQUENCH were successfully utilized which enabled the modeling of interaction between molten corium and concrete. The developed model was validated against experimental data and the results showed that the temperature of corium, composition of concrete and water injection time have a pronounced effect on mitigating depth of ablation and reactor integrity in case of a nuclear accident. In addition, the composition of concrete is the main controlling factor to mitigate ablation in the investigated case study. An alternative to concrete, could be a certain igneous rock (tested in this study), can lead to comparatively low rates of ablation due to its high thermal resistant properties. Furthermore, the injection of water (as a cooling agent) into the reactor cavity should also be optimized to enhance corium quenching to avoid ablation via basement meltthrough. As a consequence of concrete ablation by molten corium, the depth of ablation is expected to decrease to zero ablation with the suggested material in the selected case study. The concrete ablation mechanisms during MCCI are very case-dependent on the concrete solidus, liquidus and ablation temperature, respectively.
KW - Concrete Ablation
KW - Concrete Composition
KW - Corium Temperature
KW - Mitigation Scheme
KW - Molten Corium
KW - Water Injection
UR - https://www.scopus.com/pages/publications/85117721452
U2 - 10.1115/ICONE28-65217
DO - 10.1115/ICONE28-65217
M3 - Conference contribution
AN - SCOPUS:85117721452
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics
T2 - 2021 28th International Conference on Nuclear Engineering, ICONE 2021
Y2 - 4 August 2021 through 6 August 2021
ER -