1 |
Applied Programming Technology, Inc., "Symbolic Nuclear Analysis Package (SNAP) User's Manual (Version 2.6.3)", 2018.
|
2 |
Korea Institute of Nuclear Safety (KINS), "MARS-KS Code Manual Volume I: Theory Manual", KINS/RR-1822 Vol. 1, 2018.
|
3 |
International Atomic Energy Agency (IAEA), "Intercomparison and Validation of Computer Codes for Thermalhydraulics Safety Analysis of Heavy Water Reactor," TECDOC-1395, 2004.
|
4 |
International Atomic Energy Agency (IAEA), "Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data," IAEATECDOC-1688, 2012.
|
5 |
A. Oussoren and A. Delja, "Assessment of Channel Coolant Voiding in RD-14M Test Facility using TRACE," NUREG/IA-0446, 2014.
|
6 |
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.
DOI
|
7 |
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.
DOI
|
8 |
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.
DOI
|
9 |
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.
DOI
|