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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;
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Korean Nuclear Society
, v.48, no.5, pp.1059-1070,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1071-1082,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1083-1095,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1096-1108,
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5 |
Effect of DUPIC Cycle on CANDU Reactor Safety Parameters
Mohamed, Nader M.A.;Badawi, Alya;
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Korean Nuclear Society
, v.48, no.5, pp.1109-1119,
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6 |
Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results
Nasrazadani, Zahra;Behfarnia, Manochehr;Khorsandi, Jamshid;Mirvakili, Mohammad;
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Korean Nuclear Society
, v.48, no.5, pp.1120-1125,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1126-1139,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1140-1153,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1154-1161,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1162-1173,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1174-1183,
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12 |
Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants
Park, Sangjun;Park, Jinkyun;Heo, Gyunyoung;
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Korean Nuclear Society
, v.48, no.5, pp.1184-1191,
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13 |
Field Programmable Gate Array Reliability Analysis Using the Dynamic Flowgraph Methodology
McNelles, Phillip;Lu, Lixuan;
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Korean Nuclear Society
, v.48, no.5, pp.1192-1205,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1206-1218,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1219-1229,
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16 |
Experimental Investigation of Clay Fly Ash Bricks for Gamma-Ray Shielding
Mann, Harjinder Singh;Brar, Gurdarshan Singh;Mann, Kulwinder Singh;Mudahar, Gurmel Singh;
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Korean Nuclear Society
, v.48, no.5, pp.1230-1236,
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17 |
Potentiality of Using Vertical and Three-Dimensional Isolation Systems in Nuclear Structures
Zhou, Zhiguang;Wong, Jenna;Mahin, Stephen;
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Korean Nuclear Society
, v.48, no.5, pp.1237-1251,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1252-1263,
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19 |
Estimation of Leak Rate Through Cracks in Bimaterial Pipes in Nuclear Power Plants
Park, Jai Hak;Lee, Jin Ho;Oh, Young-Jin;
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Korean Nuclear Society
, v.48, no.5, pp.1264-1272,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1273-1279,
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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;
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Korean Nuclear Society
, v.48, no.5, pp.1280-1290,
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