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AUTHOR_KR:Dae-Ki Joung 861 result(s) found
 
1. Reinforcement of Polyethylene Pipes with Modified Carbon Microfibers

E. S. Petukhova;M. E. Savvinova;I. V. Krasnikova;I. V. Mishakov;A. A. Okhlopkova;Dae-Yong Jeong;Jin-Ho Cho;
Journal of the Korean Chemical Society, vol. 60, iss. 3, 2016, pp. 177-180
 
2. 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
 
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. 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
 
5. 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
 
6. 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
 
7. 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
 
8. Functionalization of 4,5-Dichloropyridazin-3(2H)-one

Gi Hyeon Sung;Bo Ram Kim;Ki Eun Ryu;Yong-Jin Yoon;
Journal of the Korean Chemical Society, vol. 58, iss. 1, 2014, pp. 140-144
 
9. SECOND ATLAS DOMESTIC STANDARD PROBLEM (DSP-02) FOR A CODE ASSESSMENT

KIM YEON-SIK ; CHOI KI-YONG ; CHO SEOK ; PARK HYUN-SIK ; KANG KYOUNG-HO ; SONG CHUL-HWA ; BAEK WON-PIL
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 871-894
 
10. ENVIRONMENTAL FATIGUE OF METALLIC MATERIALS IN NUCLEAR POWER PLANTS – A REVIEW OF KOREAN TEST PROGRAMS

JANG CHANGHEUI ; JANG HUN ; HONG JONG-DAE ; CHO HYUNCHUL ; KIM TAE SOON ; LEE JAE-GON
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 929-940