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Nuclear Engineering and Technology  

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1 Copula-based common cause failure models with Bayesian inferences
Jin, Kyungho;Son, Kibeom;Heo, Gyunyoung; / Korean Nuclear Society , v.53, no.2, pp.357-367,
2 An algorithm for evaluating time-related human reliability using instrumentation cues and procedure cues
Kim, Yochan;Kim, Jaewhan;Park, Jinkyun;Choi, Sun Yeong;Kim, Seunghwan;Jung, Wondea;Kim, Hee Eun;Shin, Seung Ki; / Korean Nuclear Society , v.53, no.2, pp.368-375,
3 Development of a human reliability analysis (HRA) guide for qualitative analysis with emphasis on narratives and models for tasks in extreme conditions
Kirimoto, Yukihiro;Hirotsu, Yuko;Nonose, Kohei;Sasou, Kunihide; / Korean Nuclear Society , v.53, no.2, pp.376-385,
4 Performing a multi-unit level-3 PSA with MACCS
Bixler, Nathan E.;Kim, Sung-yeop; / Korean Nuclear Society , v.53, no.2, pp.386-392,
5 Integrated risk assessment method for spent fuel road transportation accident under complex environment
Tao, Longlong;Chen, Liwei;Long, Pengcheng;Chen, Chunhua;Wang, Jin; / Korean Nuclear Society , v.53, no.2, pp.393-398,
6 Adaptive time-step control for modal methods to integrate the neutron diffusion equation
Carreno, A.;Vidal-Ferrandiz, A.;Ginestar, D.;Verdu, G.; / Korean Nuclear Society , v.53, no.2, pp.399-413,
7 Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Suescun-Diaz, Daniel;Espinosa-Paredes, Gilberto;Escobar, Freddy Humberto; / Korean Nuclear Society , v.53, no.2, pp.414-422,
8 Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant
Widiawati, Nina;Su'ud, Zaki;Irwanto, Dwi;Permana, Sidik;Takaki, Naoyuki;Sekimoto, Hiroshi; / Korean Nuclear Society , v.53, no.2, pp.423-429,
9 Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
Wang, Zhenyu;Liu, Shichang;She, Ding;Su, Yang;Chen, Yixue; / Korean Nuclear Society , v.53, no.2, pp.430-438,
10 Applicability research of round tube CHF mechanistic model in rod bundle channel
Liu, Wei;Peng, Shinian;Shan, Jianqiang;Jiang, Guangming;Liu, Yu;Deng, Jian;Hu, Ying; / Korean Nuclear Society , v.53, no.2, pp.439-445,
11 Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition
Gui, Minyang;Tian, Wenxi;Wu, Di;Chen, Ronghua;Su, G.H.;Qiu, Suizheng; / Korean Nuclear Society , v.53, no.2, pp.446-454,
12 Development of TREND dynamics code for molten salt reactors
Yu, Wen;Ruan, Jian;He, Long;Kendrick, James;Zou, Yang;Xu, Hongjie; / Korean Nuclear Society , v.53, no.2, pp.455-465,
13 Electrical fire simulation in control room of an AGN reactor
Jyung, Jae-Min;Chang, Yoon-Suk; / Korean Nuclear Society , v.53, no.2, pp.466-473,
14 Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations
Suman, Siddharth; / Korean Nuclear Society , v.53, no.2, pp.474-483,
15 Time uncertainty analysis method for level 2 human reliability analysis of severe accident management strategies
Suh, Young A;Kim, Jaewhan;Park, Soo Yong; / Korean Nuclear Society , v.53, no.2, pp.484-497,
16 Level 1 probabilistic safety assessment of supercritical-CO2-cooled micro modular reactor in conceptual design phase
So, Eunseo;Kim, Man Cheol; / Korean Nuclear Society , v.53, no.2, pp.498-508,
17 Preliminary analyses on decontamination factors during pool scrubbing with bubble size distributions obtained from EPRI experiments
Lee, Yoonhee;Cho, Yong Jin;Ryu, Inchul; / Korean Nuclear Society , v.53, no.2, pp.509-521,
18 ConvXGB: A new deep learning model for classification problems based on CNN and XGBoost
Thongsuwan, Setthanun;Jaiyen, Saichon;Padcharoen, Anantachai;Agarwal, Praveen; / Korean Nuclear Society , v.53, no.2, pp.522-531,
19 An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
Khambampati, Anil Kumar;Kim, Kyung Youn;Hur, Seop;Kim, Sung Joong;Kim, Jung Taek; / Korean Nuclear Society , v.53, no.2, pp.532-548,
20 Challenges of implementing the policy and strategy for management of radioactive waste and nuclear spent fuel in Indonesia
Wisnubroto, D.S.;Zamroni, H.;Sumarbagiono, R.;Nurliati, G.; / Korean Nuclear Society , v.53, no.2, pp.549-561,
21 Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes
Cognini, L.;Cechet, A.;Barani, T.;Pizzocri, D.;Van Uffelen, P.;Luzzi, L.; / Korean Nuclear Society , v.53, no.2, pp.562-571,
22 Creep and creep crack growth behaviors for base, weld, and heat affected zone in a grade 91 weldment
Kim, Woo-Gon;Sah, Injin;Kim, Seon-Jin;Lee, Hyeong-Yeon;Kim, Eung-Seon; / Korean Nuclear Society , v.53, no.2, pp.572-582,
23 Fabrication and thermal conductivity of CeO2-Ce3Si2 composite
Ahn, Jungsu;Kim, Gyeonghun;Jung, Yunsong;Ahn, Sangjoon; / Korean Nuclear Society , v.53, no.2, pp.583-591,
24 Mechanical and thermodynamic stability, structural, electronics and magnetic properties of new ternary thorium-phosphide silicides ThSixP1-x: First-principles investigation and prospects for clean nuclear energy applications
Siddique, Muhammad;Iqbal, Azmat;Rahman, Amin Ur;Azam, Sikander;Zada, Zeshan;Talat, Nazia; / Korean Nuclear Society , v.53, no.2, pp.592-602,
25 Characterization and thermophysical properties of Zr0.8Nd0.2O1.9-MgO composite
Nandi, Chiranjit;Kaity, Santu;Jain, Dheeraj;Grover, V.;Prakash, Amrit;Behere, P.G.; / Korean Nuclear Society , v.53, no.2, pp.603-610,
26 The mechanical and thermodynamic properties of α-Na3(U0.84(2),Na0.16(2))O4: A combined first-principles calculations and quasi-harmonic Debye model study
Chen, Haichuan; / Korean Nuclear Society , v.53, no.2, pp.611-617,
27 Effect of electric field on primary dark pulses in SPADs for advanced radiation detection applications
Lim, Kyung Taek;Kim, Hyoungtaek;Kim, Jinhwan;Cho, Gyuseong; / Korean Nuclear Society , v.53, no.2, pp.618-625,
28 Design of a scintillator-based prompt gamma camera for boron-neutron capture therapy: Comparison of SrI2 and GAGG using Monte-Carlo simulation
Kim, Minho;Hong, Bong Hwan;Cho, Ilsung;Park, Chawon;Min, Sun-Hong;Hwang, Won Taek;Lee, Wonho;Kim, Kyeong Min; / Korean Nuclear Society , v.53, no.2, pp.626-636,
29 Design and analysis of a free-piston stirling engine for space nuclear power reactor
Dai, Zhiwen;Wang, Chenglong;Zhang, Dalin;Tian, Wenxi;Qiu, Suizheng;Su, G.H.; / Korean Nuclear Society , v.53, no.2, pp.637-646,
30 Determination of true stress-strain curve of type 304 and 316 stainless steels using a typical tensile test and finite element analysis
Kweon, Hyeong Do;Kim, Jin Weon;Song, Ohseop;Oh, Dongho; / Korean Nuclear Society , v.53, no.2, pp.647-656,
31 Automated detection of corrosion in used nuclear fuel dry storage canisters using residual neural networks
Papamarkou, Theodore;Guy, Hayley;Kroencke, Bryce;Miller, Jordan;Robinette, Preston;Schultz, Daniel;Hinkle, Jacob;Pullum, Laura;Schuman, Catherine;Renshaw, Jeremy;Chatzidakis, Stylianos; / Korean Nuclear Society , v.53, no.2, pp.657-665,
32 Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis
Kim, Ji-Seok;Kim, Yun-Jae;Lee, Myeong-Woo;Jeon, Jun-Young;Kim, Jong-Sung; / Korean Nuclear Society , v.53, no.2, pp.666-676,
33 Exergetic design and analysis of a nuclear SMR reactor tetrageneration (combined water, heat, power, and chemicals) with designed PCM energy storage and a CO2 gas turbine inner cycle
Norouzi, Nima;Fani, Maryam;Talebi, Saeed; / Korean Nuclear Society , v.53, no.2, pp.677-687,
34 Closed-loop controller design, stability analysis and hardware implementation for fractional neutron point kinetics model
Vyawahare, Vishwesh A.;Datkhile, G.;Kadam, P.;Espinosa-Paredes, G.; / Korean Nuclear Society , v.53, no.2, pp.688-694,
35 Experimental technique for efficiency transfer along different geometries and volumes
Haddad, Kh;AL-Homyed, A.; / Korean Nuclear Society , v.53, no.2, pp.695-698,