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No Article Title /Author/Journal Title/Publication Year Cited
Statistical model for forecasting uranium prices to estimate the nuclear fuel cycle cost/
[Kim, Sungki;Ko, Wonil;Nam, Hyoon;Kim, Chulmin;Chung, Yanghon;Bang, Sungsig;] / Nuclear Engineering and Technology / 2017     		1
A Takagi-Sugeno fuzzy power-distribution method for a prototypical advanced reactor considering pump degradation/
[Yuan, Yue;Coble, Jamie;] / Nuclear Engineering and Technology / 2017     		1
Scattering cross section for various potential systems/
[Odsuren, Myagmarjav;Kato, Kiyoshi;Khuukhenkhuu, Gonchigdorj;Davaa, Suren;] / Nuclear Engineering and Technology / 2017     		0
Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design/
[Bae, Hwang;Kim, Dong Eok;Ryu, Sung-Uk;Yi, Sung-Jae;Park, Hyun-Sik;] / Nuclear Engineering and Technology / 2017     		1
The mechanical design and fabrication of 162.5 MHz buncher for China accelerator driven sub-critical system injector II/
[Niu, Haihua;Li, Youtang;He, Yuan;Zhang, Bin;Huang, Shichun;Yuan, Chenzhang;Jia, Huan;Zhang, Shenghu;] / Nuclear Engineering and Technology / 2017     		0
Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors/
[Yoon, Ji-Hyun;Lee, Bong-Sang;] / Nuclear Engineering and Technology / 2017     		0
Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark/
[Shaukat, Nadeem;Ryu, Min;Shim, Hyung Jin;] / Nuclear Engineering and Technology / 2017     		1
Development of integrated waste management options for irradiated graphite/
[Wareing, Alan;Abrahamsen-Mills, Liam;Fowler, Linda;Grave, Michael;Jarvis, Richard;Metcalfe, Martin;Norris, Simon;Banford, Anthony William;] / Nuclear Engineering and Technology / 2017     		0
ROSA/LSTF Test and RELAP5 Analyses on PWR Cold Leg Small-Break LOCA with Accident Management Measure and PKL Counterpart Test/
[Takeda, Takeshi;Ohtsu, Iwao;] / Nuclear Engineering and Technology / 2017     		0
Effect of emergency core cooling system flow reduction on channel temperature during recirculation phase of large break loss-of-coolant accident at Wolsong unit 1/
[Yu, Seon Oh;Cho, Yong Jin;Kim, Sung Joong;] / Nuclear Engineering and Technology / 2017     		1