Jun Sung Choi , Tae Hwan Kim , Jin-Woo Kim , Eung Soo Kim , Hyun Sun Park
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引用次数: 0
Abstract
This study presents the development and validation of the MCCI (Molten Core-Concrete Interaction) analysis module within the SAFARI (Safety Analysis Code For Severe Accident Risk Identification) code, a regulatory severe accident analysis tool under development in South Korea. The SAFARI code is designed to support Severe Accident Management (SAM) actions. As part of this code, a dedicated module has been developed using a Python-based computational framework specifically designed to perform MCCI analysis. Since MCCI plays a critical role in determining the progression and consequences of ex-vessel severe accidents, it is essential for the regulatory code to include a module capable of accurately analyzing MCCI behavior under a wide range of severe accident scenarios. Under these development objectives, the MCCI module incorporates multi-physics models capable of simulating key phenomena associated with corium-concrete interactions. Validation of the MCCI module was performed using experimental data from selected experiments, specifically ACE-L2, SURC-2, and CCI-2, covering validation scenarios for MCCI geometry, concrete type, and cavity conditions. The simulation results showed good agreement with experimental trends, demonstrating the module's reliability. Additionally, comparative analysis with other existing codes confirmed that the module delivers comparable performance, supporting its applicability in regulatory safety evaluations.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development