Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
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Hyunjoon Jeong
Abstract
Korea Atomic Energy Research Institute (KAERI) has operated an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) with reference to the Advanced Power Reactor 1400 MW (APR1400) for transient and design basis accidents (DBAs) simulation. An experiment for a 4-inch cold leg top-slot break was performed at ATLAS to resolve a safety issue that the loop seal reformation (LSR) of APR1400 could lead to the increase of peak cladding temperature. In addition, the experimental data has been utilized to validate system codes within a framework of domestic standard problem (DSP) program organized by KAERI in collaboration with Korea Institute of Nuclear Safety (KINS). In this study, the experiment has been analyzed by thermal-hydraulic system analysis code, MARS-KS 1.5 and a comparison with experimental and calculation results has been performed. Since the top-slot break is not a typical break geometry for safety analyses, this study aims at examining the applicability of MARS-KS to the top-slot break accident where the LSR occurs repeatedly. The results revealed that overall physical behavior during the accident was predicted by the code, appropriately. MARS-KS showed the excursion of the peak cladding temperature because of the LSR as in experiment. It has been confirmed that the core integrity was maintained because the temperature excursion by the LSR was not large enough to alter the acceptance criteria. In addition, it is presented the results of the sensitivity analysis of parameter that affect the figure of merits.
Funding source: Incheon National University
Award Identifier / Grant number: 2019
Acknowledgements
The 4th ATLAS Domestic Standard Problem (DSP-04) was organized by the Korea Atomic Energy Research Institute (KAERI) in collaboration with Korea Institute of Nuclear Safety (KINS) and supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIP) (No. 2014000501). The authors are as well grateful to the ATLAS DSP-04 program participants: KAERI for experimental data and the Council of the DSP-04 program for providing the opportunity to publish the results.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This work was supported financially by Incheon National University Research Grant in 2019.
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Declaration of competing interest: The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
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Artikel in diesem Heft
- Frontmatter
- Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
- Enhanced heat transfer in corrugated plate fin heat sink
- Discussion of options to increase the control drum worth in fast reactor
- New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
- Computational analysis of nuclear desalination system under various configurations
- Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
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- Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
- Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
- Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
- Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
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- Calendar of events
