Comparison of the Thermo-Hydraulic Response of MELCOR 1.8.6 and 2.1 for SBO Accident for APR 1400 Reactor

F. Ghaderinia, M. Rahgoshay, J. Jafari, F. S. Dauria

Abstract


An analysis of thermohydraulic response during a station blackout (SBO) accident for the APR 1400 nuclear power plant is performed using MELCOR version 1.8.6. MELCOR 1.8.6 results for the SBO scenario are benchmarked with MELCOR 2.1. The simulation of the SBO accident with MELCOR 2.1 was done by the APR 1400 reactor designer company (KEPCO). This research consists of two parts; the first part is related to the results of MELCOR 1.8.6, and the thermo-hydraulic analysis of MELCOR1.8.6 has been done. Analysis of thermohydraulic response is focused on investigating thermohydraulic parameters, such as core pressure, fuel clad temperature, water mass flow rate in the core, time of fuel clad failure, time of lower head failure, and time of containment failure. In the second part, the results of MELCOR version 1.86 have been benchmarked with the results of MELCOR 2.1. The results of the analysis of containment pressure changes in version 1.8.6 showed that the effect of pressure increase in containment is mostly due to the increase in carbon dioxide mass, but in version 2.1, the increase in pressure is more due to water vapor.

Keywords


Severe accident, Station blackout, MELCOR, Containment failure, APR1400

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References


J. H. Song, T. W. Kim, Nucl. Eng. Technol. 46 (2014) 207.

United States Nuclear Regulatory CommissionRCS (USNRC), Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, USA (1990).

T. Surbakti, S. Pinem, T. M. Sembiring et al., Atom Indones. 45 (2019) 69.

T. H. Vo and J. H. song, J. Nucl. Sci. Technol.. 54 (2017) 1074.

A. Zeighami, M. Rahgoshay, M. Khaleghi et al., Atom Indones. 43 (2017) 145.

Sandia National Laboratories (SNL), MELCOR Computer Code Manuals, reference manual Version 1.8.6 Washington, 2nd Vol, USA (2005).

Korea Atomic Energy Research Institute (KAERI), Taejon, (Korea, Republic of), MELCOR code modeling for APR1400, South Korea (2001).

Korea Electric Power Corporation (KEPCO), Standard Safety Analysis Report for APR1400 (APR1400-SSAR), South Korea (2001).

J. Park, H. Yeol Kim, S. Wang Hong, MCCI Simulation for the APR-1400 TLOFW Sequence: Transactions of the Korean Nuclear Society Spring Meeting Taebaek, Korea (2011) 569.

T. Surbakti, S. Pinem and L. Suparlina, Atom Indones. 44 (2018) 89.

I. Awad and J. Jung, Nucl. Eng. Des. 352 (2019) 110134.

D. Hartano, A. Alshamsi, A. Alsuwaidi et al., Atom Indones. 46 (2020) 177.

L. Li, M. Wang, W. Tian et al., Prog. Nucl. Energy 71 (2014) 30.

J. Heo and W. T. Kim, Study on MELCOR Modeling for Emergency External Water Injection Scenario of SBO: in APR1400, Transactions of the Korean Nuclear Society Spring Meeting (2014).

A. Antariksawan, A. Hidaka, K. Moriyama et al., Depressurization Analyses of PWR Station Blackout with MELCOR 1.8.4, Japan Atomic Energy Research Institute, Tokyo (2001).

K. Lim, Y. Cho, S. Whang et al., Ann. Nucl. Energy 109 (2017) 337.

T. Woon Kim, J. Song, V. Houng et al, Nucl. Eng. Des. 269 (2014) 155.

L. N. Kmetyk, R. K. Cole, R.C. Smith et al. MELCOR 1.8.2 Assessment: Surry PWR TMLB’ (with a DCH study). Sandia National Laboratories, Albuquerque (1994).

A. S. Ekariansyah and S. Widodo, Atom Indones. 42 (2016) 79.

S. Alhammadi, A. Alketbi, A. Eldemiery et al., Case Stud. Therm. Eng. 25 (2021) 100894.

T. Sevón, Nucl. Technol. 197 (2017) 171.

T. Sevón, Nucl. Eng. Des. 284 (2014) 80.

T. W. Kim, J. Song, V. Houng et al, Nucl. Eng. Des. 269 (2014) 155.




DOI: https://doi.org/10.55981/aij.2024.1371

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