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

Showing results 5064 to 5083 of 10267

5064
H-infinity control theory applied to xenon control for load-following operation of a nuclear reactor

Chi, SG; Cho, Nam-Zin, NUCLEAR TECHNOLOGY, v.137, no.2, pp.127 - 138, 2002-02

5065
H-mode grade confinement in L-mode edge plasmas at negative triangularity on DIII-D

Marinoni, A.; Austin, M. E.; Hyatt, A. W.; Walker, M. L.; Candy, J.; Chrystal, C.; Lasnier, C. J.; et al, PHYSICS OF PLASMAS, v.26, no.4, 2019-04

5066
$H_∞$ control theory applied to xenon control for load follow operation of a nuclear reactor = 원전의 부하추종 운전을 위한 지논 제어에 적용된 $H_∞$ 제어이론link

Chi, Sung-Goo; 지성구; et al, 한국과학기술원, 2002

5067
Half-fan-based intensity-weighted region-of-interest imaging for low-dose cone-beam CT = 저선량 콘빔 CT 를 위한 half-fan 모드에서의 세기 조절 관심 영역법link

Yoo, Bo-Yeol; 유보열; et al, 한국과학기술원, 2012

5068
Half-fan-based intensity-weighted region-of-interest imaging for low-dose cone-beam CT in image-guided radiation therapy

Yoo, Boyeol; Son, Kihong; Pua, Rizza; Kim, Jinsung; Solodov, Alexander; Cho, Seungryong, HEALTHCARE INFORMATICS RESEARCH, v.22, no.4, pp.316 - 325, 2016-10

5069
Hardness and Modulus of 410 Martensitic Steel after High Temperature Proton Irradiation

Waseem, Owais Ahmed; Ryu, Ho Jin; Jeong, Jong Ryul; Park, Byung Guk, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27

5070
Hardness of AISI Type 410 Martensitic Steels After High Temperature Irradiation via Nanoindentation

Waseem, Owais Ahmed; Jeong, Jong-Ryul; Park, Byong-Guk; Maeng, Cheol Soo; Lee, Myoung Goo; Ryu, Ho Jin, METALS AND MATERIALS INTERNATIONAL, v.23, no.6, pp.1257 - 1265, 2017-11

5071
Harness Design for the Improvement of Transmitter Survivability in a Severe Accident

Yoo, Min; Kang, Hyun Gook, American Nuclear Society 2013, American Nuclear Society, 2013-04-04

5072
HEA Phase Prediction and Principle Factor Analysis Using Machine Learning

이태규; 류호진, 33회 점단구조재료 심포지엄, 대한금속·재료학회, 2019-09-27

5073
Health and Environmental Risks of Energy Systems: Implications of Current Knowledge, Technology, and the Chernobyl Accident

Yim Man-Sung; John S. Evans; Richard Wilson, The First Saharov Memorial Conference for Peace Progress and Human Rights, no.1991, Saharov Memorial Conference for Peace Progress and Human Rights, 1991-05

5074
Heat exchanger design study for micro molten salt reactor

손인우; 최성욱; 김상지; 이정익, 2022 한국원자력학회 춘계학술발표회, 한국원자력학회, 2022-05-19

5075
Heat Flux Enhancement using Particle-mixed Coolant in HTGR

Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-03

5076
Heat Load Reduction by Additional Injection Tank on Reactor Vessel Lower Head during Severe Accident

Park, Hae Min; Jeong, Yong Hoon, The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), KNS,CNS, 2011-10-10

5077
Heat Removal Capability of the Passive Residual Heat Removal System, Proc. of Passive Safety Features in Nuclear Installations

Chun, Moon Hyun, Post-SMIRT 14 International Seminar 18, 1997

5078
Heat Transfer Coefficient Measurement at Top Region of Reactor Vessel Lower Head under IVR-ERVC Condition

Jung, Jun Yeong; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-11

5079
Heat Transfer Coefficient Measurement for Downward Facing Flow Boiling Heat Transfer to Simulate IVR-ERVC Condition of LLOCA Case

Jung, Jun Yeong; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-13

5080
Heat transfer coefficient measurement for downward-facing heat transfer on curved rectangular water channel

Jung, Jun Yeong; Jeong, Yong Hoon, 24th International Conference on Nuclear Engineering, ASME, 2016-06-27

5081
Heat transfer coefficient measurement for outer wall of the reactor vessel lower head under IVR-ERVC condition = IVR-ERVC 조건에서 원자로 하부 외벽 열전달계수 측정link

Jung, Jun Yeong; 정준영; et al, 한국과학기술원, 2016

5082
Heat Transfer Coefficient Measurement of Downward Facing Curved Surface Flow Boiling and Comparison with Prediction Correlation

Jung, Jun Yeong; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident(NUSSA (Embedded to NUTHOS-11)), Korean Nuclear Society and American Nuclear Society, 2016-10-12

5083
Heat transfer correlation for the CO2 2-phase flow near the critical point

손인우; 배성준; 이정익, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17

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