Browse > Article List
학술지 정보
Nuclear Engineering and Technology  

논문
1 Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Yoo, Jaewoon;Chang, Jinwook;Lim, Jae-Yong;Cheon, Jin-Sik;Lee, Tae-Ho;Kim, Sung Kyun;Lee, Kwi Lim;Joo, Hyung-Kook; / Korean Nuclear Society , v.48, no.5, pp.1059-1070,
2 A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Lee, Kwi Lim;Ha, Kwi-Seok;Jeong, Jae-Ho;Choi, Chi-Woong;Jeong, Taekyeong;Ahn, Sang June;Lee, Seung Won;Chang, Won-Pyo;Kang, Seok Hun;Yoo, Jaewoon; / Korean Nuclear Society , v.48, no.5, pp.1071-1082,
3 On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
Kim, Jong-Bum;Jeong, Ji-Young;Lee, Tae-Ho;Kim, Sungkyun;Euh, Dong-Jin;Joo, Hyung-Kook; / Korean Nuclear Society , v.48, no.5, pp.1083-1095,
4 Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
Lee, Chan Bock;Cheon, Jin Sik;Kim, Sung Ho;Park, Jeong-Yong;Joo, Hyung-Kook; / Korean Nuclear Society , v.48, no.5, pp.1096-1108,
5 Effect of DUPIC Cycle on CANDU Reactor Safety Parameters
Mohamed, Nader M.A.;Badawi, Alya; / Korean Nuclear Society , v.48, no.5, pp.1109-1119,
6 Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results
Nasrazadani, Zahra;Behfarnia, Manochehr;Khorsandi, Jamshid;Mirvakili, Mohammad; / Korean Nuclear Society , v.48, no.5, pp.1120-1125,
7 Implementation of Strength Pareto Evolutionary Algorithm II in the Multiobjective Burnable Poison Placement Optimization of KWU Pressurized Water Reactor
Gharari, Rahman;Poursalehi, Navid;Abbasi, Mohammadreza;Aghaie, Mahdi; / Korean Nuclear Society , v.48, no.5, pp.1126-1139,
8 Simulation of Containment Pressurization in a Large Break-Loss of Coolant Accident Using Single-Cell and Multicell Models and CONTAIN Code
Noori-Kalkhoran, Omid;Shirani, Amir Saied;Ahangari, Rohollah; / Korean Nuclear Society , v.48, no.5, pp.1140-1153,
9 Experimental Investigation of the Thermal Hydraulics in Lead Bismuth Eutectic-Helium Experimental Loop of an Accelerator-Driven System
Xi, Wenxuan;Wang, Yongwei;Li, Xunfeng;Huai, Xiulan;Cai, Jun; / Korean Nuclear Society , v.48, no.5, pp.1154-1161,
10 Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit
Perevoznikov, Sergey;Shvetsov, Yuriy;Kamayev, Aleksey;Pakhomov, Ilia;Borisov, Viacheslav;Pazin, Gennadiy;Mirzeabasov, Oleg;Korzun, Olga; / Korean Nuclear Society , v.48, no.5, pp.1162-1173,
11 Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor
Dehjourian, Mehdi;Sayareh, Reza;Rahgoshay, Mohammad;Jahanfarnia, Gholamreza;Shirani, Amir Saied; / Korean Nuclear Society , v.48, no.5, pp.1174-1183,
12 Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants
Park, Sangjun;Park, Jinkyun;Heo, Gyunyoung; / Korean Nuclear Society , v.48, no.5, pp.1184-1191,
13 Field Programmable Gate Array Reliability Analysis Using the Dynamic Flowgraph Methodology
McNelles, Phillip;Lu, Lixuan; / Korean Nuclear Society , v.48, no.5, pp.1192-1205,
14 Development of Highly Reliable Power and Communication System for Essential Instruments Under Severe Accidents in NPP
Choi, Bo Hwan;Jang, Gi Chan;Shin, Sung Min;Lee, Soo Ill;Kang, Hyun Gook;Rim, Chun Taek; / Korean Nuclear Society , v.48, no.5, pp.1206-1218,
15 Computer Modeling, Characterization, and Applications of Gallium Arsenide Gunn Diodes in Radiation Environments
El-Basit, Wafaa Abd;El-Ghanam, Safaa Mohamed;Abdel-Maksood, Ashraf Mosleh;Kamh, Sanaa Abd El-Tawab;Soliman, Fouad Abd El-Moniem Saad; / Korean Nuclear Society , v.48, no.5, pp.1219-1229,
16 Experimental Investigation of Clay Fly Ash Bricks for Gamma-Ray Shielding
Mann, Harjinder Singh;Brar, Gurdarshan Singh;Mann, Kulwinder Singh;Mudahar, Gurmel Singh; / Korean Nuclear Society , v.48, no.5, pp.1230-1236,
17 Potentiality of Using Vertical and Three-Dimensional Isolation Systems in Nuclear Structures
Zhou, Zhiguang;Wong, Jenna;Mahin, Stephen; / Korean Nuclear Society , v.48, no.5, pp.1237-1251,
18 Numerical Ductile Tearing Simulation of Circumferential Cracked Pipe Tests under Dynamic Loading Conditions
Nam, Hyun-Suk;Kim, Ji-Soo;Ryu, Ho-Wan;Kim, Yun-Jae;Kim, Jin-Weon; / Korean Nuclear Society , v.48, no.5, pp.1252-1263,
19 Estimation of Leak Rate Through Cracks in Bimaterial Pipes in Nuclear Power Plants
Park, Jai Hak;Lee, Jin Ho;Oh, Young-Jin; / Korean Nuclear Society , v.48, no.5, pp.1264-1272,
20 Validation of a New Design of Tellurium Dioxide-Irradiated Target
Fllaoui, Aziz;Ghamad, Younes;Zoubir, Brahim;Ayaz, Zinel Abidine;Morabiti, Aissam El;Amayoud, Hafid;Chakir, El Mahjoub; / Korean Nuclear Society , v.48, no.5, pp.1273-1279,
21 Estimation of Probability Density Functions of Damage Parameter for Valve Leakage Detection in Reciprocating Pump Used in Nuclear Power Plants
Lee, Jong Kyeom;Kim, Tae Yun;Kim, Hyun Su;Chai, Jang-Bom;Lee, Jin Woo; / Korean Nuclear Society , v.48, no.5, pp.1280-1290,