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Nuclear Engineering and Technology  

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1 Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis
Galahom, A. Abdelghafar;Mohsen, Mohamed Y.M.;Amrani, Naima; / Korean Nuclear Society , v.54, no.1, pp.1-10,
2 Possibility of curium as a fuel for VVER-1200 reactor
Shelley, Afroza;Ovi, Mahmud Hasan; / Korean Nuclear Society , v.54, no.1, pp.11-18,
3 Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARK
Zhao, Chen;Peng, Xingjie;Zhang, Hongbo;Zhao, Wenbo;Li, Qing;Chen, Zhang; / Korean Nuclear Society , v.54, no.1, pp.19-29,
4 On-line measurement and simulation of the in-core gamma energy deposition in the McMaster nuclear reactor
Alqahtani, Mohammed; / Korean Nuclear Society , v.54, no.1, pp.30-35,
5 Application of POD reduced-order algorithm on data-driven modeling of rod bundle
Kang, Huilun;Tian, Zhaofei;Chen, Guangliang;Li, Lei;Wang, Tianyu; / Korean Nuclear Society , v.54, no.1, pp.36-48,
6 Preconditioned Jacobian-free Newton-Krylov fully implicit high order WENO schemes and flux limiter methods for two-phase flow models
Zhou, Xiafeng;Zhong, Changming;Li, Zhongchun;Li, Fu; / Korean Nuclear Society , v.54, no.1, pp.49-60,
7 Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling
Wang, Chenglong;Li, Panxiao;Zhang, Dalin;Tian, Wenxi;Qiu, Suizheng;Su, G.H.;Deng, Jian; / Korean Nuclear Society , v.54, no.1, pp.61-71,
8 Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
Song, Min Seop;Park, Il Woong;Kim, Eung Soo;Lee, Yeon-Gun; / Korean Nuclear Society , v.54, no.1, pp.72-83,
9 Sensitivity analysis of input variables to establish fire damage thresholds for redundant electrical panels
Kim, Byeongjun;Lee, Jaiho;Shin, Weon Gyu; / Korean Nuclear Society , v.54, no.1, pp.84-96,
10 CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment
Ye, Linrong;Yu, Hao;Wang, Mingjun;Wang, Qianglong;Tian, Wenxi;Qiu, Suizheng;Su, G.H.; / Korean Nuclear Society , v.54, no.1, pp.97-109,
11 How to incorporate human failure event recovery into minimal cut set generation stage for efficient probabilistic safety assessments of nuclear power plants
Jung, Woo Sik;Park, Seong Kyu;Weglian, John E.;Riley, Jeff; / Korean Nuclear Society , v.54, no.1, pp.110-116,
12 Study on blockage after downward discharge of the molten metallic fuel with radiographic visualization
Lee, Min Ho;Jerng, Dong Wook;Bang, In Cheol; / Korean Nuclear Society , v.54, no.1, pp.117-129,
13 Ignition and flame propagation in hydrogen-air layers from a geological nuclear waste repository: A preliminary study
Ryu, Je Ir;Woo, Seung Min;Lee, Manseok;Yoon, Hyun Chul; / Korean Nuclear Society , v.54, no.1, pp.130-137,
14 Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment
Gao, Pengcheng;Zhang, Bin;Li, Jishen;Shan, Jianqiang; / Korean Nuclear Society , v.54, no.1, pp.138-151,
15 Analysis of steam generator tube rupture accidents for the development of mitigation strategies
Bang, Jungjin;Choi, Gi Hyeon;Jerng, Dong-Wook;Bae, Sung-Won;Jang, Sunghyon;Ha, Sang Jun; / Korean Nuclear Society , v.54, no.1, pp.152-161,
16 Numerical analysis of melt migration and solidification behavior in LBR severe accident with MPS method
Wang, Jinshun;Cai, Qinghang;Chen, Ronghua;Xiao, Xinkun;Li, Yonglin;Tian, Wenxi;Qiu, Suizheng;Su, G.H.; / Korean Nuclear Society , v.54, no.1, pp.162-176,
17 Analyses of hydrogen risk in containment filtered venting system using MELCOR
Choi, Gi Hyeon;Jerng, Dong-Wook;Kim, Tae Woon; / Korean Nuclear Society , v.54, no.1, pp.177-185,
18 Analysis of pipe thickness reduction according to pH in FAC facility with In situ ultrasonic measurement real time monitoring
Oh, Se-Beom;Kim, Jongbeom;Lee, Jong-Yeon;Kim, Dong-Jin;Kim, Kyung-Mo; / Korean Nuclear Society , v.54, no.1, pp.186-192,
19 Localization and size estimation for breaks in nuclear power plants
Lin, Ting-Han;Chen, Ching;Wu, Shun-Chi;Wang, Te-Chuan;Ferng, Yuh-Ming; / Korean Nuclear Society , v.54, no.1, pp.193-206,
20 Experimental investigation on effect of ion cyclotron resonance heating on density fluctuation in SOL at EAST
Li, Y.C.;Li, M.H.;Wang, M.;Liu, L.;Zhang, X.J.;Qin, C.M.;Wang, Y.F.;Wu, C.B.;Liu, L.N.;Xu, J.C.;Ding, B.J.;Lin, X.D.;Shan, J.F.;Liu, F.K.;Zhao, Y.P.;Zhang, T.;Gao, X.; / Korean Nuclear Society , v.54, no.1, pp.207-219,
21 Study on volume reduction of radioactive perlite thermal insulation waste by heat treatment with potassium carbonate
Chou, Yi-Sin;Singh, Bhupendra;Chen, Yong-Song;Yen, Shi-Chern; / Korean Nuclear Society , v.54, no.1, pp.220-225,
22 Phase-field simulation of radiation-induced bubble evolution in recrystallized U-Mo alloy
Jiang, Yanbo;Xin, Yong;Liu, Wenbo;Sun, Zhipeng;Chen, Ping;Sun, Dan;Zhou, Mingyang;Liu, Xiao;Yun, Di; / Korean Nuclear Society , v.54, no.1, pp.226-233,
23 Structural and radiological characterization of irradiated RBMK-1500 reactor graphite
Lagzdina, Elena;Lingis, Danielius;Plukis, Arturas;Plukiene, Rita;Germanas, Darius;Garbaras, Andrius;Garankin, Jevgenij;Gudelis, Arunas;Ignatjev, Ilja;Niaura, Gediminas;Krutovcov, Sergej;Remeikis, Vidmantas; / Korean Nuclear Society , v.54, no.1, pp.234-243,
24 Mechanical performance of additively manufactured austenitic 316L stainless steel
Kim, Kyu-Tae; / Korean Nuclear Society , v.54, no.1, pp.244-254,
25 FTIR study of gamma and electron irradiated high-density polyethylene for high dose measurements
Al-Ghamdi, Hanan;Farah, Khaled;Almuqrin, Aljawharah;Hosni, Faouzi; / Korean Nuclear Society , v.54, no.1, pp.255-261,
26 Neutronic design of pulsed neutron facility (PNF) for PGNAA studies of biological samples
Oh, Kyuhak; / Korean Nuclear Society , v.54, no.1, pp.262-268,
27 Radionuclide identification method for NaI low-count gamma-ray spectra using artificial neural network
Qi, Sheng;Wang, Shanqiang;Chen, Ye;Zhang, Kun;Ai, Xianyun;Li, Jinglun;Fan, Haijun;Zhao, Hui; / Korean Nuclear Society , v.54, no.1, pp.269-274,
28 Fractional radioactive decay law and Bateman equations
Cruz-Lopez, C.A.;Espinosa-Paredes, G.; / Korean Nuclear Society , v.54, no.1, pp.275-282,
29 Study on gamma radiation attenuation and non-ionizing shielding effectiveness of niobium-reinforced novel polymer composite
Akman, Ferdi.;Ogul, H.;Ozkan, I.;Kacal, M.R.;Agar, O.;Polat, H.;Dilsiz, K.; / Korean Nuclear Society , v.54, no.1, pp.283-292,
30 Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning
Yang, Li-qun;Liu, Yong-kuo;Peng, Min-jun;Ayodeji, Abiodun;Chen, Zhi-tao;Long, Ze-yu; / Korean Nuclear Society , v.54, no.1, pp.293-300,
31 Calculation of X-ray spectra characteristics and kerma to personal dose equivalent Hp(10) conversion coefficients: Experimental approach and Monte Carlo modeling
Arectout, A.;Zidouh, I.;Sadeq, Y.;Azougagh, M.;Maroufi, B.;Chakir, E.;Boukhal, H.; / Korean Nuclear Society , v.54, no.1, pp.301-309,
32 A comparative study on applicability and efficiency of machine learning algorithms for modeling gamma-ray shielding behaviors
Bilmez, Bayram;Toker, Ozan;Alp, Selcuk;Oz, Ersoy;Icelli, Orhan; / Korean Nuclear Society , v.54, no.1, pp.310-317,
33 Synthesis of barium-doped PVC/Bi2WO6 composites for X-ray radiation shielding
Gholamzadeh, Leila;Sharghi, Hamed;Aminian, Mohsen Khajeh; / Korean Nuclear Society , v.54, no.1, pp.318-325,
34 Comparative analyses of a shield building subjected to a large commercial aircraft impact between decoupling method and coupling method
Han, Pengfei;Liu, Jingbo;Fei, Bigang; / Korean Nuclear Society , v.54, no.1, pp.326-342,
35 Round robin analysis to investigate sensitivity of analysis results to finite element elastic-plastic analysis variables for nuclear safety class 1 components under severe seismic load
Kim, Jun-Young;Lee, Jong Min;Park, Jun Geun;Kim, Jong-Sung;Cho, Min Ki;Ahn, Sang Won;Koo, Gyeong-Hoi;Lee, Bong Hee;Huh, Nam-Su;Kim, Yun-Jae;Kim, Jong-In;Nam, Il-Kwun; / Korean Nuclear Society , v.54, no.1, pp.343-356,
36 Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module
Zhang, Peiyao;Guo, Quanquan;Pang, Sen;Sun, Yunlun;Chen, Yan; / Korean Nuclear Society , v.54, no.1, pp.357-373,
37 Design and analysis of isolation effectiveness for three-dimensional base-seismic isolation of nuclear island building
Zhu, Xiuyun;Lin, Gao;Pan, Rong;Li, Jianbo; / Korean Nuclear Society , v.54, no.1, pp.374-385,
38 Seismic performance assessment of NPP concrete containments considering recent ground motions in South Korea
Kim, Chanyoung;Cha, Eun Jeong;Shin, Myoungsu; / Korean Nuclear Society , v.54, no.1, pp.386-400,
39 Analytical method to estimate cross-section stress profiles for reactor vessel nozzle corners under internal pressure
Oh, Changsik;Lee, Sangmin;Jhung, Myung Jo; / Korean Nuclear Society , v.54, no.1, pp.401-413,
40 Radioactive waste sampling for characterisation - A Bayesian upgrade
Pyke, Caroline K.;Hiller, Peter J.;Koma, Yoshikazu;Ohki, Keiichi; / Korean Nuclear Society , v.54, no.1, pp.414-422,