과제정보
This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety(KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission(NSSC) of the Republic of Korea. (No. 1805003)
참고문헌
- Korea Institute of Nuclear Safety (KINS), "MARS-KS Code Manual Volume I: Theory Manual", KINS/RR-1822 Vol. 1, 2018.
- International Atomic Energy Agency (IAEA), "Intercomparison and Validation of Computer Codes for Thermalhydraulics Safety Analysis of Heavy Water Reactor," TECDOC-1395, 2004.
- International Atomic Energy Agency (IAEA), "Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data," IAEATECDOC-1688, 2012.
- A. Oussoren and A. Delja, "Assessment of Channel Coolant Voiding in RD-14M Test Facility using TRACE," NUREG/IA-0446, 2014.
- S. O. Yu, M. K. Cho and K. L. Baek, "Numerical Assessment of LOCA Experiments of RD-14M Using MARS-KS Code," International Journal of Advanced Nuclear Reactor Design and Technology, Vol. 2, pp. 1-9, 2020. https://doi.org/10.1016/j.jandt.2020.04.001
- H. T. Kim, B. W. Rhee and J. H. Park, "A Blind Simulation of RD-14M Small-Break LOCA Experiments Using CATHENA Code", Annals of Nuclear Energy, Vol. 38, pp. 389-403, 2011. https://doi.org/10.1016/j.anucene.2010.10.002
- H. T. Kim, "An Open Calculation of RD-14M Small-Break LOCA Experiments Using CATHENA Code," Annals of Nuclear Energy, Vol. 46, pp. 63-75, 2012. https://doi.org/10.1016/j.anucene.2012.03.006
- A. Dixit, S. K. Yadav, N. Kumar, T. A. Khan, S. Hajela and M. Singhal, "Validation of Computer Code 'ATMIKA' against RD-14M Small Break LOCA Experiments," Nuclear Engineering and Design, Vol. 323, pp. 427-433, 2017. https://doi.org/10.1016/j.nucengdes.2017.07.042
- Applied Programming Technology, Inc., "Symbolic Nuclear Analysis Package (SNAP) User's Manual (Version 2.6.3)", 2018.