Browse "NE-Conference Papers(학술회의논문)" by Title 

Showing results 2301 to 2320 of 5619

2301
Experiment on ELM mitigation control with SMBI and RMP in KSTAR

Lee, HY; Hahn, SH; Lee, JH; Ko, WH; Juhn, JW; Han, H; Yoon, SW; et al, 42nd European Physical Society Conference on Plasma Physics, European Physical Society, 2015-06-22

2302
Experiment on Pool and Flow Boiling CHF for the SiC Surfaces under Atmospheric Condition

Kam, Dong Hoon; Lee, Jong Hyuk; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-25

2303
Experiment Study of the chracteristics of pool boiling CHF enhancement using water-based magnetic fluid

Lee, Taeseung; Jeong, Yong Hoon, 한국원자력학회 2011년도 춘계학술대회 (Korean Nuclear Society Spring Meeting), 한국원자력학회, 2011-05-25

2304
Experiment Study on the Magnetic Field Effect of Pool Boiling CHF Enhancement in Water-based Magnetic Fluid with Lower Concentration

Lee, Jong Hyuk; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02

2305
Experimental Analysis of Specification Language Impact on NPP Software Diversity

Yoo, Chang Sik; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.76 - 76, 한국원자력학회, 1998-10

2306
Experimental analysis of the flow behavior in the safety injection tank of APR1400

Jeong, Woon Ho; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09-07

2307
Experimental analysis of the flow in the vortex chamber of the safety injection tank for APR1400

Jeong, Woonho; Jeong, Yong Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), Thermal Hydraulics Divisions of AESJ, KNS, 2016-11-28

2308
Experimental and Analytical Study on the Simulation of Pool Boiling CHF Based on Macrolayer Dryout Model

Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24

2309
Experimental and CFD analysis of condensation with non-condensable gas in multi-tubes

Kim, Do Yun; No, Hee-Cheon; Jeon, Byong Guk, ANS2016, ANS2016, 2016-11-10

2310
Experimental and CFD Analysis of Printed Circuit Heat Exchanger for Supercritical CO2 Power Cycle Application

Baik, Seung Joon; Kim, Hyeon Tae; Kim, Seong Gu; Lee, Je Kyoung; Lee, Jeong Ik, The Korean Nuclear Society Autumn Meeting (2015), The Korean Nuclear Society, 2015-10-29

2311
Experimental and computational analysis of gas natural circulation loop

Lee, JeongIk; Hejzlar,P, International Congress on Advances in Nuclear Power Plants (ICAPP 2007), French Nuclear Energy Society, 2007-05-14

2312
Experimental and Numerical Analysis of S-CO2 Critical Flow for SFR Recovery System Design

Kim, Mim Seok; Jung, Hwa Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05

2313
Experimental and Numerical Investigations on S-CO2 Critical Flow with Implications in Turbomachinery Seal Design

Kim, Min Seok; Jung, Hwa-Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong-Ik, The 9th National Congress of Fluids Engineering, 한국가시화정보학회, 2016-08-10

2314
Experimental and Numerical Studies of Supercritical CO2 Test Loop with GAMMA code

Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Lee, Jeong-Ik, NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety(2016), American Nuclear Society, 2016-10-09

2315
EXPERIMENTAL AND NUMERICAL STUDY OF CRITICAL FLOW MODEL DEVELOPMENT FOR SUPERCRITICAL CO2 POWER CYCLE APPLICATION

KIM, MINSEOK; Oh, Bong-seong; Jung, Hwa-Young; Bae, Seong Jun; Lee, Jeong-Ik, ASME Turbo Expo 2018: Turbomachinery Technical Conference and Exposition, ASME, 2018-06-13

2316
Experimental and Numerical Study of Supercritical CO₂ Test Loop Transient Conditions

Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Baik, Seungjoon; Lee, Jekyoung; Lee, Jeong-Ik, The First Pacific Rim Thermal Engineering Conference(2016), American Society of Thermal and Fluids Engineers, 2016-03-13

2317
Experimental Approach to Effect Estimation of Decision Support Systems

이승준; 성풍현, 한국원자력학회 2007 춘계학술발표대회, 한국원자력학회, 2007-05-10

2318
Experimental Approaches on Flow Accelerated Corrosion Behavior of CANDU Feeder Piping

Kim, In Sup, The 4th International Workshop on the Integrity of Nuclear Components, 2002

2319
Experimental Assessment of Critical Heat Flux for the Real Condition of IVR-ERVC Strategy

Park, Hae Min; 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, 2016-10-12

2320
Experimental CHF Study on the Effect of Heater Material and Coolant Additives for the Top of the Reactor Vessel Lower Head

Park, Hae Min; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-16

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