Severe accident in high-power light water reactors: Mitigating strategies, assessment methods and research opportunities

MA Amidu, SA Olatubosun, A Ayodeji… - Progress in Nuclear Energy, 2022 - Elsevier
The advancement in innovative high-power reactors necessitates concurrent study on the
core failure modes and severe accident scenarios, towards a better reactor design. This …

A comparative study on the effect of reactor cavity shape and location of reactor vessel on the shape of particle bed formed in pre-flooded reactor cavity using the CFD …

H Na, N Cho - Progress in Nuclear Energy, 2025 - Elsevier
Using the CFD-DEM method, numerical calculations are conducted to analyze the shape of
particle beds formed in two small-sized pre-flooded reactor cavities, aiming to understand …

Evaluation of dryout region in a heap-like debris bed formed in an APR1400 pre-flooded reactor cavity

H Na, JH Kim, DH Shin, HC Kim, SC Kim - Annals of Nuclear Energy, 2023 - Elsevier
This study evaluates how large a debris bed becomes dryout during ex-vessel cooling in a
pre-flooded reactor cavity if a postulated severe accident occurs. It is assumed that all …

Experimental study on the penetration characteristics of leaking molten salt in the thermal insulation layer of aluminum silicate fiber

Y Wang, J Tian, SW Wang, C Zhou… - Nuclear Science and …, 2021 - Springer
The molten salt leakage accident is an important issue in the nuclear safety analysis of
molten salt reactors. While the molten salt leaks from the pipeline or storage tank, it will …

A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity

H Na, DG Kang, S Pak, HJ Lee - Annals of Nuclear Energy, 2021 - Elsevier
We develop an analytical model about concrete ablation during ex-vessel cooling in a pre-
flooded cavity. The model considers the melting of dry debris bed, the formation of crust, the …

[HTML][HTML] Numerical investigation of spreading phenomena of molten corium using EISPH method

HS Yoo, ES Kim - Nuclear Engineering and Technology, 2024 - Elsevier
Understanding the behavior of molten corium is crucial for effective heat management and
ensuring the integrity of reactor containment during severe nuclear incidents. Corium …

A computational model for molten corium spreading and solidification

A Kucala, R Rao, L Erickson - Computers & Fluids, 2019 - Elsevier
When the core is breached during a severe nuclear accident, a molten mixture of nuclear
fuel, cladding, and structural supports is discharged from the reactor vessel. This molten …

Evaluation of the dryout region of heat-generating conical porous beds

H Na, H Kim, YS Lee - Progress in Nuclear Energy, 2023 - Elsevier
This study evaluates how multi-phase fluids flow and how a large volume becomes a dryout
region in a volumetrically heat-generating conical porous bed formed in the pre-flooded …

One-dimensional ex-vessel coolability analysis of debris beds formed in OPR1000 pre-flooded reactor cavity

H Na, DG Kang, YH Ryu, HJ Lee - Annals of Nuclear Energy, 2020 - Elsevier
This paper presents a feasibility study on a pre-flooded cavity strategy for cooling molten
corium in OPR1000 nuclear power plants. The characteristics of debris beds formed in the …

Concrete ablation depth analysis method during top water flooding ex-vessel cooling by considering phenomena in dry and flooded conditions

H Na - Progress in Nuclear Energy, 2022 - Elsevier
This study proposes a method to analyze the concrete ablation depth during top water
flooding ex-vessel cooling by considering the phenomena occurring in dry and flooded …