Acknowledgement
This work was performed within the program of the sixth ATLAS Domestic Standard Problem (DSP-06), which was organized by Korea Atomic Energy Research Institute (KAERI) in collaboration with the Korea Institute of Nuclear Safety (KINS) under the national nuclear R&D program funded by the Ministry of Education (MOE) of the Korean government. The authors are also grateful to the sixth ATLAS DSP-06 program participant: KAERI for the experimental data and to the council of the sixth DSP-06 program for providing the opportunity to publish the results.
References
- S. J. Ha, et al., "Development of the SPACE Code for Nuclear Power Plant", Nuclear Eng. and Tech., Vol. 43, 45-62, 2011. https://doi.org/10.5516/NET.2011.43.1.045
- J. K. Song, "Thermal-hydraulic Analysis of Operator Action Time on Coping Strategy of LUHS Event for OPR1000", J. Korean Soc. Saf., Vol. 35, No. 5, pp. 121-127, 2021.
- H. J. Jeong et al., "Analysis of MSGTR-PAFS Accident of the ATLAS using the MARS-KS Code", J. Korean Soc. Saf., Vol. 36, No. 3, pp. 74-80, 2021.
- Yonhap News Agency, https://bit.ly/3JYgtQL, 2020.05.
- J. B. Lee et al., "Test Result on a Small Break Loss-of-coolant Accident Simulation for the Control Rod Driving Mechanism Nozzle Rupture with a Failure of Safety Injection Pump using the ATLAS Facility", Transactions of the Korean Nuclear Society Virtual spring Meeting, May 13-14, 2021.
- The Korea Atomic Energy Research Institute (KAERI), "Description report of ATLAS Facility and Instrumentation", KAERI/TR-8106/2020, 2020.
- J. A. Trapp and V. H. Ransom, "A Chocked-flow Calculation Criterion for Nonhomogenous, Nonequilibrium, Two-phase Flows ", Int. J. Multiphase Flow, Vol. 8, No. 6, pp. 669-681, 1982. https://doi.org/10.1016/0301-9322(82)90070-2
- F. J. Moody, "Maximum Flow Rate of a Single Component, Two-phase Mixture", Int. J. Heat Transfer, Vol. 87, No. 1, pp. 134-141, 1965. https://doi.org/10.1115/1.3689029
- KHNP, "SPACE 3.22 Manual Volume 4: Developmental Assessment Problems", 2021.