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AUTHOR_KR:Geun-Pyo Hong 210 result(s) found
 
1. Spectroscopic Properties and Ligand Field Analysis of trans-[Cr(Me2tn)2(OH)(H2O)](ClO4)2

Jong-Ha Choi;Keon Sang Ryoo;Yong Pyo Hong;
Journal of the Korean Chemical Society, vol. 58, iss. 6, 2014, pp. 681-685
 
2. EUTECTIC(LiCl-KCl) WASTE SALT TREATMENT BY SEQUENCIAL SEPARATION PROCESS

CHO YUNG-ZUN ; LEE TAE-KYO ; CHOI JUNG-HUN ; EUN HEE-CHUL ; PARK HWAN-SEO ; PARK GEUN-IL
Nuclear Engineering and Technology, vol. 45, iss. 5, 2013, pp. 675-682
 
3. A REVIEW ON THE ODSCC OF STEAM GENERATOR TUBES IN KOREAN NPPS

CHUNG HANSUB ; KIM HONG-DEOK ; OH SEUNGJIN ; BOO MYUNG HWAN ; NA KYUNG-HWAN ; YUN EUNSUP ; KANG YONG-SEOK ; KIM WANG-BAE ; LEE JAE GON ; KIM DONG-JIN ; KIM HONG PYO
Nuclear Engineering and Technology, vol. 45, iss. 4, 2013, pp. 513-522
 
4. SUSCEPTIBILITY OF ALLOY 690 TO STRESS CORROSION CRACKING IN CAUSTIC AQUEOUS SOLUTIONS

KIM DONG-JIN ; KIM HONG PYO ; HWANG SEONG SIK
Nuclear Engineering and Technology, vol. 45, iss. 1, 2013, pp. 67-72
 
5. ROLE OF GRAIN BOUNDARY CARBIDES IN CRACKING BEHAVIOR OF Ni BASE ALLOYS

HWANG SEONG SIK ; LIM YUN SOO ; KIM SUNG WOO ; KIM DONG JIN ; KIM HONG PYO
Nuclear Engineering and Technology, vol. 45, iss. 1, 2013, pp. 73-80
 
6. EVALUATION OF GALVANIC CORROSION BEHAVIOR OF SA-508 LOW ALLOY STEEL AND TYPE 309L STAINLESS STEEL CLADDING OF REACTOR PRESSURE VESSEL UNDER SIMULATED PRIMARY WATER ENVIRONMENT

Kim, Sung-Woo;Kim, Dong-Jin;Kim, Hong-Pyo;
Nuclear Engineering and Technology, vol. 44, iss. 7, 2012, pp. 773-780
 
7. RELATIONSHIP BETWEEN RADIATION INDUCTED YIELD STRENGTH INCREMENT AND CHARPY TRANSITION TEMPERATURE SHIFT IN REACTOR PRESSURE VESSEL STEELS OF KOREAN NUCLEAR POWER PLANTS

Lee, Gyeong-Geun;Lee, Yong-Bok;Kwon, Jun-Hyun;
Nuclear Engineering and Technology, vol. 44, iss. 5, 2012, pp. 543-550
 
8. ASSESSMENT OF POSSIBILITY OF PRIMARY WATER STRESS CORROSION CRACKING OCCURRENCE BASED ON RESIDUAL STRESS ANALYSIS IN PRESSURIZER SAFETY NOZZLE OF NUCLEAR POWER PLANT

Lee, Kyoung-Soo;Kim, W.;Lee, Jeong-Geun;
Nuclear Engineering and Technology, vol. 44, iss. 3, 2012, pp. 343-354
 
9. INVESTIGATION ON MATERIAL DEGRADATION OF ALLOY 617 IN HIGH TEMPERATURE IMPURE HELIUM COOLANT

Kim, Dong-Jin;Lee, Gyeong-Geun;Jeong, Su-Jin;Kim, Woo-Gon;Park, Ji-Yeon;
Nuclear Engineering and Technology, vol. 43, iss. 5, 2011, pp. 429-436
 
10. PYROPROCESSING TECHNOLOGY DEVELOPMENT AT KAERI

Lee, Han-Soo;Park, Geun-Il;Kang, Kweon-Ho;Hur, Jin-Mok;Kim, Jeong-Guk;Ahn, Do-Hee;Cho, Yung-Zun;Kim, Eung-Ho;
Nuclear Engineering and Technology, vol. 43, iss. 4, 2011, pp. 317-328