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Nuclear Engineering and Technology  

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1 A new perspective towards the development of robust data-driven intrusion detection for industrial control systems
Ayodeji, Abiodun;Liu, Yong-kuo;Chao, Nan;Yang, Li-qun; / Korean Nuclear Society , v.52, no.12, pp.2687-2698,
2 Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator
Abdelhameed, Ahmed Amin E.;Chaudri, Khurrum Saleem;Kim, Yonghee; / Korean Nuclear Society , v.52, no.12, pp.2699-2708,
3 Application of deep neural networks for high-dimensional large BWR core neutronics
Abu Saleem, Rabie;Radaideh, Majdi I.;Kozlowski, Tomasz; / Korean Nuclear Society , v.52, no.12, pp.2709-2716,
4 Comprehensive validation of silicon cross sections
Czakoj, Tomas;Kostal, Michal;Simon, Jan;Soltes, Jaroslav;Marecek, Martin;Capote, Roberto; / Korean Nuclear Society , v.52, no.12, pp.2717-2724,
5 Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library
Hartanto, Donny;Liem, Peng Hong; / Korean Nuclear Society , v.52, no.12, pp.2725-2732,
6 An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis
Lin, Ching-Sheng;Yang, Won Sik; / Korean Nuclear Society , v.52, no.12, pp.2733-2742,
7 Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code
Kim, Mun Soo;Jeong, Yong Hoon; / Korean Nuclear Society , v.52, no.12, pp.2743-2759,
8 Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon
Jha, Alok;Gupta, Anurag;Das, Rajarshi;Paraswar, Shantanu D.; / Korean Nuclear Society , v.52, no.12, pp.2760-2770,
9 Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution
Al-Yahia, Omar S.;Yoon, Ho Joon;Jo, Daeseong; / Korean Nuclear Society , v.52, no.12, pp.2771-2788,
10 Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor
Zhao, Pengcheng;Liu, Zijing;Yu, Tao;Xie, Jinsen;Chen, Zhenping;Shen, Chong; / Korean Nuclear Society , v.52, no.12, pp.2789-2802,
11 CFD study of the PTS experiment in ROCOM test facility
Carija, Zoran;Ledic, Fran;Sikirica, Ante;Niceno, Bojan; / Korean Nuclear Society , v.52, no.12, pp.2803-2811,
12 Effects of house load operation on PSA based on operational experiences in Korea
Lim, Hak Kyu;Park, Jong-hoon; / Korean Nuclear Society , v.52, no.12, pp.2812-2820,
13 Parameter importance ranking for SBLOCA of CPR1000 with moment-independent sensitivity analysis
Xiong, Qingwen;Gou, Junli;Shan, Jianqiang; / Korean Nuclear Society , v.52, no.12, pp.2821-2835,
14 Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model
Kim, Yeon Soo;Jeon, Joongoo;Song, Chang Hyun;Kim, Sung Joong; / Korean Nuclear Society , v.52, no.12, pp.2836-2846,
15 On-site water level measurement method based on wavelength division multiplexing for harsh environments in nuclear power plants
Lee, Hoon-Keun;Choo, Jaeyul;Shin, Gangsig;Kim, Sung-Man; / Korean Nuclear Society , v.52, no.12, pp.2847-2851,
16 Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR
Saghafi, Mahdi;Ayyoubzadeh, Seyed Mohsen;Terman, Mohammad Sadegh; / Korean Nuclear Society , v.52, no.12, pp.2852-2859,
17 Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation
Ding, Xiao-Yu;Xu, Qiu;Zhu, Xiao-yong;Luo, Lai-Ma;Huang, Jian-Jun;Yu, Bin;Gao, Xiang;Li, Jian-Gang;Wu, Yu-Cheng; / Korean Nuclear Society , v.52, no.12, pp.2860-2866,
18 Restoration of the isotopic composition of reprocessed uranium hexafluoride using cascade with additional product
Palkin, Valerii;Maslyukov, Eugenii; / Korean Nuclear Society , v.52, no.12, pp.2867-2873,
19 Novel homogeneous burnable poisons in pressurized water reactor ceramic fuel
Dodd, Brandon;Britt, Taylor;Lloyd, Cody;Shah, Manit;Goddard, Braden; / Korean Nuclear Society , v.52, no.12, pp.2874-2879,
20 Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors
Jung, Tae-Sik;Na, Yeon-Soo;Joo, Min-Jae;Lim, Kwang-Young;Kim, Yoon-Ho;Lee, Seung-Jae; / Korean Nuclear Society , v.52, no.12, pp.2880-2886,
21 Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Khvostov, G.; / Korean Nuclear Society , v.52, no.12, pp.2887-2900,
22 Thermal creep behavior of CZ cladding under biaxial stress state
Jin, Xin;Lin, Yuyu;Zhang, Libin; / Korean Nuclear Society , v.52, no.12, pp.2901-2909,
23 Performance of 3D printed plastic scintillators for gamma-ray detection
Kim, Dong-geon;Lee, Sangmin;Park, Junesic;Son, Jaebum;Kim, Tae Hoon;Kim, Yong Hyun;Pak, Kihong;Kim, Yong Kyun; / Korean Nuclear Society , v.52, no.12, pp.2910-2917,
24 Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads
Kim, Jong-Sung;Kim, Jun-Young; / Korean Nuclear Society , v.52, no.12, pp.2918-2927,
25 Entropy and exergy analysis and optimization of the VVER nuclear power plant with a capacity of 1000 MW using the firefly optimization algorithm
Talebi, Saeed;Norouzi, Nima; / Korean Nuclear Society , v.52, no.12, pp.2928-2938,
26 Analytic responses of slender beams supported by rotationally restrained hinges during support motions
Ryu, Jeong Yeon;Kim, Yong-Woo; / Korean Nuclear Society , v.52, no.12, pp.2939-2948,
27 Crack growth analysis and remaining life prediction of dissimilar metal pipe weld joint with circumferential crack under cyclic loading
Murthy, A. Ramachandra;Gandhi, P.;Vishnuvardhan, S.;Sudharshan, G.; / Korean Nuclear Society , v.52, no.12, pp.2949-2957,
28 Analyzing local perceptions toward the new nuclear research reactor in Thailand
Tantitaechochart, Sarasinee;Paoprasert, Naraphorn;Silva, Kampanart; / Korean Nuclear Society , v.52, no.12, pp.2958-2968,
29 Is nuclear energy a better alternative for mitigating CO2 emissions in BRICS countries? An empirical analysis
Hassan, Syed Tauseef;Danish, Danish;khan, Salah-Ud-Din;Baloch, Muhammad Awais;Tarar, Zahid Hassan; / Korean Nuclear Society , v.52, no.12, pp.2969-2974,
30 Evaluation of the radiation damage effect on mechanical properties in Tehran research reactor (TRR) clad
Amirkhani, Mohamad Amin;Khoshahval, Farrokh; / Korean Nuclear Society , v.52, no.12, pp.2975-2981,