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Nuclear Engineering and Technology  

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1 Bubbly, Slug, and Annular Two-Phase Flow in Tight-Lattice Subchannels
Prasser, Horst-Michael;Bolesch, Christian;Cramer, Kerstin;Ito, Daisuke;Papadopoulos, Petros;Saxena, Abhishek;Zboray, Robert; / Korean Nuclear Society , v.48, no.4, pp.847-858,
2 Computational Fluid Dynamic Simulation of Single Bubble Growth under High-Pressure Pool Boiling Conditions
Murallidharan, Janani;Giustini, Giovanni;Sato, Yohei;Niceno, Bojan;Badalassi, Vittorio;Walker, Simon P.; / Korean Nuclear Society , v.48, no.4, pp.859-869,
3 Key Findings from the Artist Project on Aerosol Retention in a Dry Steam Generator
Dehbi, Abdelouahab;Suckow, Detlef;Lind, Terttaliisa;Guentay, Salih;Danner, Steffen;Mukin, Roman; / Korean Nuclear Society , v.48, no.4, pp.870-880,
4 Large Scale Experiments Simulating Hydrogen Distribution in a Spent Fuel Pool Building During a Hypothetical Fuel Uncovery Accident Scenario
Mignot, Guillaume;Paranjape, Sidharth;Paladino, Domenico;Jaeckel, Bernd;Rydl, Adolf; / Korean Nuclear Society , v.48, no.4, pp.881-892,
5 Design of an Organic Simplified Nuclear Reactor
Shirvan, Koroush;Forrest, Eric; / Korean Nuclear Society , v.48, no.4, pp.893-905,
6 Mass Transfer Experiments for the Heat Load During In-Vessel Retention of Core Melt
Park, Hae-Kyun;Chung, Bum-Jin; / Korean Nuclear Society , v.48, no.4, pp.906-914,
7 Single Bubble Dynamic Behavior in AL2O3/H2O Nanofluid on Downward-Facing Heating Surface
Wang, Yun;Wu, Junmei; / Korean Nuclear Society , v.48, no.4, pp.915-924,
8 Analytical Modeling of Natural Convection in a Tall Rectangular Enclosure with Multiple Disconnected Partitions
Bae, Youngmin;Kim, Seong Hoon;Seo, Jae-Kwang;Kim, Young In; / Korean Nuclear Society , v.48, no.4, pp.925-931,
9 Enhancement of Pool Boiling Heat Transfer in Water Using Sintered Copper Microporous Coatings
Jun, Seongchul;Kim, Jinsub;Son, Donggun;Kim, Hwan Yeol;You, Seung M.; / Korean Nuclear Society , v.48, no.4, pp.932-940,
10 Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model
Farkas, Istvan;Hutli, Ezddin;Farkas, Tatiana;Takacs, Antal;Guba, Attila;Toth, Ivan; / Korean Nuclear Society , v.48, no.4, pp.941-951,
11 Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor
Ahn, Sang June;Ha, Kwi-Seok;Chang, Won-Pyo;Kang, Seok Hun;Lee, Kwi Lim;Choi, Chi-Woong;Lee, Seung Won;Yoo, Jin;Jeong, Jae-Ho;Jeong, Taekyeong; / Korean Nuclear Society , v.48, no.4, pp.952-964,
12 Study of the Effect of (U0.8Pu0.2)O2 Uranium-Plutonium Mixed Fuel Fission Products on a Living Organism
Baimukhanova, Ayagoz;Kim, Dmitriy;Zhumagulova, Roza;Tazhigulova, Bibinur;Zharaspayeva, Gulzhanar;Azhiyeva, Galiya; / Korean Nuclear Society , v.48, no.4, pp.965-974,
13 Effect of Spray System on Fission Product Distribution in Containment During a Severe Accident in a Two-Loop Pressurized Water Reactor
Dehjourian, Mehdi;Rahgoshay, Mohammad;Sayareh, Reza;Jahanfarnia, Gholamreza;Shirani, Amir Saied; / Korean Nuclear Society , v.48, no.4, pp.975-981,
14 Novel Roaming and Stationary Tethered Aerial Robots for Continuous Mobile Missions in Nuclear Power Plants
Gu, Beom W.;Choi, Su Y.;Choi, Young Soo;Cai, Guowei;Seneviratne, Lakmal;Rim, Chun T.; / Korean Nuclear Society , v.48, no.4, pp.982-996,
15 Chemical Stability of Conductive Ceramic Anodes in LiCl-Li2O Molten Salt for Electrolytic Reduction in Pyroprocessing
Kim, Sung-Wook;Kang, Hyun Woo;Jeon, Min Ku;Lee, Sang-Kwon;Choi, Eun-Young;Park, Wooshin;Hong, Sun-Seok;Oh, Seung-Chul;Hur, Jin-Mok; / Korean Nuclear Society , v.48, no.4, pp.997-1001,
16 Modeling of Pore Coarsening in the Rim Region of High Burn-up UO2 Fuel
Xiao, Hongxing;Long, Chongsheng; / Korean Nuclear Society , v.48, no.4, pp.1002-1008,
17 Effect of Ti and Si Interlayer Materials on the Joining of SiC Ceramics
Jung, Yang-Il;Park, Jung-Hwan;Kim, Hyun-Gil;Park, Dong-Jun;Park, Jeong-Yong;Kim, Weon-Ju; / Korean Nuclear Society , v.48, no.4, pp.1009-1014,
18 Safety Classification of Systems, Structures, and Components for Pool-Type Research Reactors
Kim, Tae-Ryong; / Korean Nuclear Society , v.48, no.4, pp.1015-1021,
19 Study on the Structure Optimization and the Operation Scheme Design of a Double-Tube Once-Through Steam Generator
Wei, Xinyu;Wu, Shifa;Wang, Pengfei;Zhao, Fuyu; / Korean Nuclear Society , v.48, no.4, pp.1022-1035,
20 PWSCC Growth Assessment Model Considering Stress Triaxiality Factor for Primary Alloy 600 Components
Kim, Jong-Sung;Kim, Ji-Soo;Jeon, Jun-Young;Kim, Yun-Jae; / Korean Nuclear Society , v.48, no.4, pp.1036-1046,
21 Development of Field Programmable Gate Array-based Reactor Trip Functions Using Systems Engineering Approach
Jung, Jaecheon;Ahmed, Ibrahim; / Korean Nuclear Society , v.48, no.4, pp.1047-1057,