1 L. Tsungnan, "What to remember: how memory order affects the performance of NARX neural networks" 2 : 1051-1056, 1998
2 Takeshi Takeda, "Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs" 한국원자력학회 50 (50): 829-841, 2018
3 A. Petruzzi, "Thirty years’ experience in RELAP5 applications at GRNSPG & NINE" 193 : 47-87, 2016
4 S. H. Park, "Smart sensing of the RPV water level in NPP severe accidents using a GMDH algorithm" 61 : 931-938, 2014
5 EPRI, "Severe Accident Management Guidance Technical Basis Report, Volumes 2: The Physics of Accident Progression" 2012
6 Z. -Q. Wang, "Remaining useful life prediction of degrading systems subjected to imperfect maintenance : application to draught fans" 100 : 802-813, 2018
7 Takeshi Takeda, "ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature" 한국원자력학회 50 (50): 1412-1420, 2018
8 D. Y. Kim, "Prediction of leak flow rate using fuzzy neural networks in severe post-LOCA circumstances" 61 : 3644-3652, 2014
9 D. Roverso, "Plant diagnostics by transient classification : the aladdin approach" 17 : 767-790, 2002
10 L. Tsungnan, "Learning long-term dependencies in NARX recurrent neural networks" 7 : 1329-1338, 1996
1 L. Tsungnan, "What to remember: how memory order affects the performance of NARX neural networks" 2 : 1051-1056, 1998
2 Takeshi Takeda, "Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs" 한국원자력학회 50 (50): 829-841, 2018
3 A. Petruzzi, "Thirty years’ experience in RELAP5 applications at GRNSPG & NINE" 193 : 47-87, 2016
4 S. H. Park, "Smart sensing of the RPV water level in NPP severe accidents using a GMDH algorithm" 61 : 931-938, 2014
5 EPRI, "Severe Accident Management Guidance Technical Basis Report, Volumes 2: The Physics of Accident Progression" 2012
6 Z. -Q. Wang, "Remaining useful life prediction of degrading systems subjected to imperfect maintenance : application to draught fans" 100 : 802-813, 2018
7 Takeshi Takeda, "ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature" 한국원자력학회 50 (50): 1412-1420, 2018
8 D. Y. Kim, "Prediction of leak flow rate using fuzzy neural networks in severe post-LOCA circumstances" 61 : 3644-3652, 2014
9 D. Roverso, "Plant diagnostics by transient classification : the aladdin approach" 17 : 767-790, 2002
10 L. Tsungnan, "Learning long-term dependencies in NARX recurrent neural networks" 7 : 1329-1338, 1996
11 M. Saghafi, "Introduction of a research project on development of accident management support tool for BNPP (WWER-1000) based on the lessons learned from Fukushima accident" 2015
12 M. Boroushaki, "Identification of a nuclear reactor core(VVER)using recurrent neural networks" 29 : 1225-1240, 2002
13 M. Marseguerra, "Identification of a line break by a neural network methodology" 21 : 249-258, 1994
14 M. G. Na, "Estimation of break location and size for loss of coolant accidents using neural networks" 232 : 289-300, 2004
15 S. H. Lee, "Diagnostics of loss of coolant accidents using SVC and GMDH models" 58 : 267-276, 2011
16 T. V. Santosh, "Diagnostic system for identification of accident scenarios in nuclear power plants using artificial neural networks" 94 : 759-762, 2009
17 M. Saghafi, "Development and qualification of a thermal-hydraulic nodalization for modeling station blackout accident in PSBVVER test facility" 303 : 109-121, 2016
18 M. Saghafi, "Determination of PAR configuration for PWR containment design : a hydrogen mitigation strategy" 42 : 7104-7119, 2017
19 M. G. Na, "Detection and diagnostics of loss of coolant accidents using support vector machines" 55 : 628-636, 2008
20 J.M. Izquierdo, "Current Status and Applications of Integrated Safety Assessment and Simulation Code System for ISA" 한국원자력학회 49 (49): 295-305, 2017
21 S. J. Lee, "Computational Intelligence in Nuclear Applications : lessons Learned and Recent DevelopmentsA dynamic neural network based accident diagnosis advisory system for nuclear power plants" 46 : 268-281, 2005
22 P. Baraldi, "Clustering for unsupervised fault diagnosis in nuclear turbine shut-down transients" 58-59 : 160-178, 2015
23 M. Saghafi, "Application of FFTBM with signal mirroring to improve accuracy assessment of MELCOR code" 308 : 238-251, 2016
24 이성욱, "Analysis of Uncertainty Quantification Method by Comparing Monte-Carlo Method and Wilks' Formula" 한국원자력학회 46 (46): 481-488, 2014
25 M. Saghafi, "Accident management support tools in nuclear power plants : a post-Fukushima review" 92 : 1-14, 2016
26 K. Mo, "A dynamic neural network aggregation model for transient diagnosis in nuclear power plants" 49 : 262-272, 2007