Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title 

Showing results 3741 to 3760 of 10300

3741
Effect of Film Thickness on the Columnar Packing Structures of Discotic Supramolecules in Thin Films

Kim, Hyo-Sik; Choi, Sung-Min; Pate, Brian D.; Park, Po-Gyu, CHEMPHYSCHEM, v.10, no.15, pp.2642 - 2646, 2009-10

3742
Effect of flash dimentions and billet size in closed-die forging of an aluminium alloy part

Gangshu Shen; Im, Yong-Taek; Taylan Altan, NAMRC, pp.34, The Ohio State University, 1989-05

3743
Effect of Focal Spot Size on Dose Calculation of a ZnWO4 Thin-Film Scintillator for High-Resolution X-ray Imaging

이재우; 이주혁; 정헌용; 조성오, 한국원자력학회 2022 춘계학술발표회, 한국원자력학회, 2022-05-19

3744
Effect of fulvic acid on the sorption of Se(IV) onto kaolinite, montmorillonite, and illite-smectite mixed layer = 카올리나이트, 몬모릴로나이트, 일라이트-스멕타이트 혼합층광물에 대한 셀레늄(IV) 수착반응에 미치는 풀빅산의 영향link

Eun, Hyeonjin; Yun, Jong-Il; et al, 한국과학기술원, 2023

3745
Effect of Geometry, Heater Material and Coolant Additives on CHF of Curved Inclined Surface

Park, Hae Min; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2012-09

3746
Effect of Ground Surface Roughness on Atmospheric Dispersion and Dry Deposition of Cs-137 in the UAE Environment

Kim, Sung-yeop; Beeley, Philip A.; Chang, Soon-Heung; Lee, Kun Jai, 2013 한국원자력학회 춘계학술발표회, 한국원자력학회, 2013-05-30

3747
Effect of Heat Flux on Concentration Feactor in Crevices of Tube Support Plates of Nuclear Steam Generators

노희천; 신상운, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984

3748
Effect of heat treatment on corrosion behaviour of additively manufactured 316L stainless steel in high-temperature water

Xiao, Qian; Chen, Junjie; Lee, Hyeon Bae; Jang, Changheui; Jang, Kyungnam, CORROSION SCIENCE, v.210, 2023-01

3749
Effect of heat treatment on fatigue crack propagation of inconel 690 = Inconel 690의 피로균열전파에 미치는 열처리의 영향link

Kim, Young-Ho; 김영호; et al, 한국과학기술원, 1996

3750
Effect of heat treatment on grain boundary carbides and primary water stress corrosion cracking resistance of Alloy 182 weld

Kim, Ho-Sub; Chen, Junjie; Lee, Hyeon Bae; Shin, Ji Ho; Kong, Byeong Seo; Oh, Seungjin; Jang, Hun; et al, CORROSION SCIENCE, v.191, 2021-10

3751
Effect of heat treatment on microstructure and mechanical properties of 12% Cr steel = 열처리가 12% Cr 강의 미세 조직과 기계적 성질에 미치는 영향link

Kim, Hong-Deuk; 김홍덕; et al, 한국과학기술원, 1994

3752
Effect of Heat Treatment on Microstructure and Mechanical Properties of 12%Cr Steel, Hangzou, China

Kim, In Sup, 1st Pacific Rim International Conference on Advanced Materials and Processing, pp.23 - 27, 1992

3753
Effect of Heat Treatment on the Microstructure and Mechanical Properties of 12% Cr Steel

김인섭, Proc. of the 3rd Symposium on Phase Transformation, Seoul, Korea, 1991

3754
Effect of Heat Treatment on the Microstucture Texture and Mechanical Properties of Zircaloy-4

김인섭, Fall Meeting of Korean Nuclear Society, 1989

3755
EFFECT OF HEAT-FLUX ON THE CONCENTRATION FACTOR IN CREVICES OF NUCLEAR STEAM-GENERATORS

SHIN, SW; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.73, no.3, pp.378 - 383, 1986-06

3756
Effect of heat-treatment on delayed hydride cracking in Zr-2.5wt%Nb pressure tube material = 열처리가 Zr-2.5wt%Nb 압력관 재료의 지체균열전파에 미치는 영향link

Oh, Je-Yong; 오제용; et al, 한국과학기술원, 1996

3757
Effect of Heater Material and Additives on Critical Heat Flux for the IVR-ERVC Strategy

Park, Hae Min; Jeong, Yong Hoon, The 6th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics, Korean Nuclear Society, 2013-04-11

3758
Effect of heater material and coolant additives on CHF for a downward facing curved surface

Park, Hae Min; Jeong, Yong-Hoon; Heo, Sun, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.344 - 351, 2014-10

3759
Effect of high temperature steam oxidation on yielding of zircaloy-4 PWR cladding tubes through expandingcopper mandrel test = 구리 맨드렐 팽창시험법을 이용한 가압경수형 피복관 지르칼로이-4 의 항복에 대한 고온 수증기 산화의 영향link

Nho, Kye-Ho; 노계호; et al, 한국과학기술원, 1989

3760
Effect of hydride morphology on fracture toughness of Russian pressure tube materials

김인섭, Proceeding of the Korean Nuclear Society Automn meeting, pp.100 -, 1997

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