Advanced
Insert title here
 Search Results
KEYWORD_EN:Alloy 24 result(s) found
 
1. DETECTION OF ODSCC IN SG TUBES DEPENDING ON THE SIZE OF THE CRACK AND ON THE PRESENCE OF SLUDGE DEPOSITS

Chung, Hansub;Kim, Hong-Deok;Kang, Yong-Seok;Lee, Jae-Gon;Nam, Minwoo;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 869-874
 
2. HEAT-UP AND COOL-DOWN TEMPERATURE-DEPENDENT HYDRIDE REORIENTATION BEHAVIORS IN ZIRCONIUM ALLOY CLADDING TUBES

Won, Ju-Jin;Kim, Myeong-Su;Kim, Kyu-Tae;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 681-688
 
3. SCANNING ELECTRON MICROSCOPY ANALYSIS OF FUEL/MATRIX INTERACTION LAYERS IN HIGHLY-IRRADIATED U-Mo DISPERSION FUEL PLATES WITH Al AND Al-Si ALLOY MATRICES

Keiser, Dennis D. Jr.;Jue, Jan-Fong;Miller, Brandon D.;Gan, Jian;Robinson, Adam B.;Medvedev, Pavel;Madden, James;Wachs, Dan;Meyer, Mitch;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 147-158
 
4. A MICROSTRUCTURAL MODEL OF THE THERMAL CONDUCTIVITY OF DISPERSION TYPE FUELS WITH A FUEL MATRIX INTERACTION LAYER

WILLIAMS A.F. ; LEITCH B.W. ; WANG N.
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 839-845
 
5. 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
 
6. EFFECTS OF IRRADIATION ON THERMAL CONDUCTIVITY OF ALLOY 690 AT LOW NEUTRON FLUENCE

RYU WOO SEOG ; PARK DAE GYU ; SONG UNG SUP ; PARK JIN SEOK ; AHN SANG BOK
Nuclear Engineering and Technology, vol. 45, iss. 2, 2013, pp. 219-222
 
7. 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
 
8. 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
 
9. PFM APPLICATION FOR THE PWSCC INTEGRITY OF Ni-BASE ALLOY WELDS-DEVELOPMENT AND APPLICATION OF PINEP-PWSCC

Hong, Jong-Dae;Jang, Changheui;Kim, Tae Soon;
Nuclear Engineering and Technology, vol. 44, iss. 8, 2012, pp. 961-970
 
10. 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