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AUTHOR_KR:Heung-Ryeol Kho 129 result(s) found
 
1. OPTIMIZATION OF OPERATION PARAMETERS OF 80-KEV ELECTRON GUN

Kim, Jeong Dong;Lee, Yongdeok;Kang, Heung Sik;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 387-394
 
2. LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS

Lee, Je-Whan;Jeong, Yong-Hoon;Chang, Yoon-Il;Chang, Soon-Heung;
Nuclear Engineering and Technology, vol. 43, iss. 4, 2011, pp. 383-390
 
3. AN EXPERIMENTAL STUDY ON AN ELECTROCHEMICAL REDUCTION OF AN OXIDE MIXTURE IN THE ADVANCED SPENT-FUEL CONDITIONING PROCESS

Jeong, Sang-Mun;Park, Byung-Heung;Hur, Jin-Mok;Seo, Chung-Seok;Lee, Han-Soo;Song, Kee-Chan;
Nuclear Engineering and Technology, vol. 42, iss. 2, 2010, pp. 183-192
 
4. A DYNAMIC SIMULATION OF THE SULFURIC ACID DECOMPOSITION PROCESS IN A SULFUR-IODINE NUCLEAR HYDROGEN PRODUCTION PLANT

Shin, Young-Joon;Chang, Ji-Woon;Kim, Ji-Hwan;Park, Byung-Heung;Lee, Ki-Young;Lee, Won-Jae;Chang, Jong-Hwa;
Nuclear Engineering and Technology, vol. 41, iss. 6, 2009, pp. 831-840
 
5. AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

Kang, Hyun-Gook;Kim, Man-Cheol;Lee, Seung-Jun;Lee, Ho-Jung;Eom, Heung-Seop;Choi, Jong-Gyun;Jang, Seung-Cheol;
Nuclear Engineering and Technology, vol. 41, iss. 6, 2009, pp. 849-858
 
6. ESTIMATION OF THE FISSION PRODUCTS, ACTINIDES AND TRITIUM OF HTR-10

Jeong, Hye-Dong;Chang, Soon-Heung;
Nuclear Engineering and Technology, vol. 41, iss. 5, 2009, pp. 729-738
 
7. CRITICAL HEAT FLUX ENHANCEMENT

Chang, Soon-Heung;Jeong, Yong-Hoon;Shin, Byung-Soo;
Nuclear Engineering and Technology, vol. 38, iss. 8, 2006, pp. 753-762
 
8. ANALYSIS OF THE OPTIMIZED H TYPE GRID SPRING BY A CHARACTERIZATION TEST AND THE FINITE ELEMENT METHOD UNDER THE IN-GRID BOUNDARY CONDITION

Yoon Kyung-Ho;Lee Kang-Hee;Kang Heung-Seok;Song Kee-Nam;
Nuclear Engineering and Technology, vol. 38, iss. 4, 2006, pp. 375-382
 
9. FLUID-ELASTIC INSTABILITY OF ROTATED SQUARE TUBE ARRAY IN AN AIR-WATER TWO-PHASE CROSSFLOW

CHUNG HEUNG JUNE;CHU IN-CHEOL;
Nuclear Engineering and Technology, vol. 38, iss. 1, 2006, pp. 69-80
 
10. CORE DESIGN FOR HETEROGENEOUS THORIUM FUEL ASSEMBLIES FOR PWR (II) - THERMAL HYDRAULIC ANALYSIS AND SPENT FUEL CHARACTERISTICS

BAE KANG-MOK;HAN KYU-HYUN;KIM MYUNG-HYUN;CHANG SOON-HEUNG;
Nuclear Engineering and Technology, vol. 37, iss. 4, 2005, pp. 363-374