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AUTHOR_KR:Ki-Hwan Hwang 981 result(s) found
 
1. INVESTIGATION ON EFFECTS OF ENLARGED PIPE RUPTURE SIZE AND AIR PENETRATION TIMING IN REAL-SCALE EXPERIMENT OF SIPHON BREAKER

Kang, Soon Ho;Lee, Kwon-Yeong;Lee, Gi Cheol;Kim, Seong Hoon;Chi, Dae Young;Seo, Kyoungwoo;Yoon, Juhyeon;Kim, Moo Hwan;Park, Hyun Sun;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 817-824
 
2. DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

Tak, Nam-Il;Lee, Sung Nam;Kim, Min-Hwan;Lim, Hong Sik;Noh, Jae Man;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 641-654
 
3. EFFECTS OF TEMPERING AND PWHT ON MICROSTRUCTURES AND MECHANICAL PROPERTIES OF SA508 GR.4N STEEL

Lee, Ki-Hyoung;Jhung, Myung Jo;Kim, Min-Chul;Lee, Bong-Sang;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 413-422
 
4. IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR

Kim, Hyun-Gil;Park, Jeong-Yong;Jeong, Yong-Hwan;Koo, Yang-Hyun;Yoo, Jong-Sung;Mok, Yong-Kyoon;Kim, Yoon-Ho;Suh, Jung-Min;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 423-430
 
5. PUMP DESIGN AND COMPUTATIONAL FLUID DYNAMIC ANALYSIS FOR HIGH TEMPERATURE SULFURIC ACID TRANSFER SYSTEM

Choi, Jung-Sik;Shin, Young-Joon;Lee, Ki-Young;Yun, Yong-Sup;Choi, Jae-Hyuk;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 363-372
 
6. PREDICTION OF THE REACTOR VESSEL WATER LEVEL USING FUZZY NEURAL NETWORKS IN SEVERE ACCIDENT CIRCUMSTANCES OF NPPS

Park, Soon Ho;Kim, Dae Seop;Kim, Jae Hwan;Na, Man Gyun;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 373-380
 
7. EVALUATION OF THE APPLICABLE REACTIVITY RANGE OF A REACTIVITY COMPUTER FOR A CANDU-6 REACTOR

Lee, Eun Ki;Park, Dong Hwan;Lee, Whan Soo;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 183-194
 
8. SPECTRUM WEIGHTED RESPONSES OF SEVERAL DETECTORS IN MIXED FIELDS OF FAST AND THERMAL NEUTRONS

Kim, Sang In;Chang, Insu;Kim, Bong Hwan;Kim, Jang Lyul;Lee, Jung Il;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 273-280
 
9. ON-POWER DETECTION OF PIPE WALL-THINNED DEFECTS USING IR THERMOGRAPHY IN NPPS

Kim, Ju Hyun;Yoo, Kwae Hwan;Na, Man Gyun;Kim, Jin Weon;Kim, Kyeong Suk;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 225-234
 
10. IMPACT ANALYSES AND TESTS OF CONCRETE OVERPACKS OF SPENT NUCLEAR FUEL STORAGE CASKS

Lee, Sanghoon;Cho, Sang-Soon;Jeon, Je-Eon;Kim, Ki-Young;Seo, Ki-Seog;
Nuclear Engineering and Technology, vol. 46, iss. 1, 2014, pp. 73-80