Browse "NE-Conference Papers(학술회의논문)" by Author 240

Showing results 96 to 155 of 233

96
ECC Water Bypass in the Downcomer with DVI of APR1400 under LBLOCA

No, Hee Cheon; Lee, Dong Won, 한국원자력학회 춘계발표회, 한국원자력학회, 2002

97
ECC Water bypass in the Downcomer with DVI of APR1400 under LBLOCA

No, Hee Cheon; Lee, DW, Proc. of the Int. Conf. on the New Frontiers of Nuclear Technology, 2002

98
ECC Water Film Spreading, ECC Water Bypass and Sweep-out Phenomena in the Downcomer with DVI of APR1400 under LBLOCA

No, Hee Cheon; Lee, DW, Proc. of the Int. Congress on Advanced Nuclear Power Plant, 2002

99
Effect of Heat Flux on Concentration Feactor in Crevices of Tube Support Plates of Nuclear Steam Generators

노희천; 신상운, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984

100
Effect of Interfacial Drag Force on the Numerical Stability of the Two-Fluid Model

노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1988

101
EFFECTS OF ONSET TIME OF NATURAL CIRCULATION ON SAFETY IN THE AIR-INGRESS ACCIDENT OF HTGRS

No Hee Cheon; Jin, Hyung Gon, NTHAS7, 2010-11

102
Estimation of graphite density and mechanical strength of VHTR during air-ingress accident

Kim, E.S.; Oh, C.H.; No, Hee Cheon; Kim, B.J., 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007-09-30

103
Evaluation of Fuel Performance in PWR After Cladding Defect

노희천; 송성일, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984

104
Experiment and model development on the effect of burn-off for graphite oxidation

Kim, E.S.; No, Hee Cheon, 2006 Annual Meeting - American Nuclear Society, pp.670 - 671, 2006-06-04

105
Experiment and RELAP5 analysis for the downcomer boiling of APR1400 under LBLOCA

Lee, D.W.; No, Hee Cheon; Lee, E.H.; Oh, S.J.; Song, C.-H., Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1612 - 1617, 2004-06-13

106
Experimental Studies of Bunsen section for over-azeotropic condition in I-S cycle

Yoon, Ho Joon; No, Hee Cheon; Kim, Young Soo; Jin, Hyung Gon; Lee, Jeong-Ik; Lee, Byung Jin, 한국원자력학회 춘계발표회, 한국원자력학회, 2009

107
Experimental Studies of Flooding in Nearly Horizontal Pipes

No, Hee Cheon; Choi, Ki Yong, 한국원자력학회 춘계발표회, pp.107 - 113, 한국원자력학회, 1993

108
Experimental study of liquid holdup in pressurizer in case of loss-of-residual heat removal during mid-loop operation

No, Hee Cheon; MOON, Young Min, 한국원자력학회 추계발표회, 한국원자력학회, 2001

109
Experimental Study on Fracture of Oxidized Support Column in VHTR

No Hee Cheon; Park, Byung Ha, ANS, 2011-06

110
Experimental study on the film spreading, sweep-out of ECC water in the downcomer with DVI under LBLOCA

No, Hee Cheon; Lee, Dong Won, 한국원자력학회 추계발표회, 한국원자력학회, 2001

111
Experimental Sutdies of Flooding in Nearly Horizontal Pipes

No, Hee Cheon; Choi, KY, Proceedings of the International Confefence on Multiphase Flow, 1995

112
Experimental validation of an optimal operating window of bunsen section in iodine-sulfur thermo-chemical water splitting cycle

Yoon, H.J.; No, Hee Cheon; Kim, Y.S.; Jin, H.G., 2nd International Topical Meeting o`n Safety and Technology of Nuclear Hydrogen Production, Control, and Management 2010, pp.63 - 67, 2010-06-13

113
Experiments on the onset of water accumulation and CCFL through a multi-hole plate in a vertical tank

No, Hee Cheon; Lee, Kyung-Won; Song, Chul-Hwa, 한국원자력학회 춘계발표회, 한국원자력학회, 2004

114
Failure of oxidized graphite support column in VHTR

Park, B.H.; No, Hee Cheon, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.342 - 349, 2010-06-13

115
Flash distillation of overazeotropic HIx phase based on optimal Bunsen reaction in I-S cycle

Yoon, H.J.; No, Hee Cheon; Kim, Y.S.; Jin, H.G., 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.722 -, 2009-06-14

116
Fluent의 삼차원 LES 난류 모델을 이용한 가압 경수로 연료봉 다발에서 멱 스펙트럼 밀도의 해석

노희천; 김현민, 한국원자력학회 춘계발표회, 한국원자력학회, 2003

117
Full_scale simulation of a dry storage cask by computational fluid dynamics

No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2010

118
GAMMA Air Ingress Analysis for a Pebble-Bed Gas-Cooled Reactor

No, Hee Cheon; Lim, Hong-Sik, KNS Spring Meeting, Korean Nuclear Society, 2005-05-26

119
GAMMA Air Ingress Analysis for a Pebble-Bed Gas-Cooled Reactor

No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2005

120
GAMMA Validation with the HTTR RCCS Mockup Test for the Assesment of Decay Heat Removal of GCRs Under Accident Conditions

No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 추계발표회, 한국원자력학회, 2004

121
Gravity injection experiments and direct contact condensation regime map for passive high-pressure injection system

No, Hee Cheon; Lee, Sang Il, Proc. of the 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operation,a nd safety, 1997

122
Helium Hydraulic Tests in the Printed Circuit Heat Exchanger

노희천; Kim, In Hun; Lee, Cheol Shin, 한국원자력학회 춘계발표회, 한국원자력학회, 2008

123
Helium-water loop tests with PCHE for GAMMA validations

No, Hee Cheon; Kim, In Hun, 한국원자력학회 추계발표회, 한국원자력학회, 2011

124
High temperature and high pressure experiment of HI decomposition in the IS process

Y. Ho Joon; No, Hee Cheon; L. Byung Jin; K. Seung Jun; K. Eung Soo, 2007 Winter Meeting on International Conference on Making the Renaissance Real, pp.349 - 350, 2007-11-11

125
High Temperature Boric Acid Solubility during Post-LOCA Long-term Cooling Period

No, Hee Cheon, NUTHOS-7 2008, 2008-10-05

126
High temperature boric acid solubility during post-LOCA long-term cooling period

Kim, Y.S.; No, Hee Cheon; Lee, E.H.; Yoo, S.H.; Kim, H.M.; Lee, S.I.; Kim, C.H.; et al, 2008 Winter Meeting and Nuclear Technology Expo: Nuclear Power-Ready, Steady, Go, pp.489 - 490, 2008-11-09

127
Horizon expansion of thermal-hydraulic activities into HTGR safety analysis including gas-turbine cycle and hydrogen plant

No, Hee Cheon; Yoon, H.J.; Kim, S.J.; Lee, B.J.; Kim, J.H.; Kim, H.M.; Lim, H.S., 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007-09-30

128
Hyperbolicity Breaking and Flooding

노희천; 정지환; 이재영, 한국원자력학회 추계발표회, pp.159 - 164, 한국원자력학회, 1992

129
Hyperbolicity Breaking and Flooding

No, Hee Cheon, Fifth International Meeting on Reactor Thermal Hydraulics, soft Lake City, Utah, 1992

130
Hyperbolicity Breaking and The Effects of Entrance and Exit Geometry on Flooding

No, Hee Cheon; Jeong, Ji Hwan; Lee, Jae Young, 1993 International Heat Transfer Conference, 1993

131
Hyperbolicity Breaking Model and drift-Flux Model for the Prediction of flow Regime Transition after Inverted Annular Flow

No, Hee Cheon; Jeong, Hae Yong, 한국원자력학회 추계발표회, pp.456 - 461, 1995

132
Implementation of 3-field model into TRAC

No, Hee Cheon; Lee, Sang Ik, 한국원자력학회 춘계발표회, 한국원자력학회, 2001

133
Implementation of entrainment modeling into TRAC-M

No, Hee Cheon; Lee, IS; Cho, CS, NURETH10, 2003

134
Improvement of Direct Contact Condensation Model of RELAP5/MOD3.1 for Passive High-Pressure Injection System

No, Hee Cheon; Lee, Sang Il, 한국원자력학회 춘계발표회, pp.368 - 373, 한국원자력학회, 1996

135
Improvement of direct contact condensation model of RELAP5/MOD3.1 for passive high-pressure injection system

No, Hee Cheon; Lee, SI, Proc. of the Int. Topical Meeting on Advanced Reactors Safety, pp.983 - 992, 1997

136
Improvement of neumann's model for binary and ternary mixtures in the HI section of SI thermo-chemical water splitting cycle

Kim, S.-J.; No, Hee Cheon; Lee, B.J.; Yoon, H.J.; Kim, E.S., 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management, pp.147 - 153, 2007-06-24

137
Improvement of Safety Analysis Methodology for CANDU Reactors: Off-take Experiment at T-junction between Header and Feeder Pipes with Arbitrary Angles in CANDU

No, Hee Cheon; Hwang, Ki Suk; Lee, Jae Young; MOON, Young Min; Yu, Sun Oh; Kim, Manwoong; Kim, Huo Jun, 한국원자력학회 춘계발표회, 한국원자력학회, 2003

138
Improvement of the CCFL Model of the RELAP5/MOD3.2B Code in a Horizontal Pipe

No, Hee Cheon; Heo, Sun, 한국원자력학회 춘계발표회, 한국원자력학회, 1999

139
Interrelationship Between the Drift-Flax Model and the Two-Fluid Model

노희천, 한국원자력학회 추계발표회, 한국원자력학회, 1991

140
Iterative and Non-Iterative Condensation Models for Steam Condensation with Noncondensable Gas in a Vertical Tube

No, Hee Cheon; Park, HS, Proc. of the 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998

141
KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRS: SPACE AND GAMMA

No Hee Cheon, NURETH-14, 2011-09

142
Liquid Entrainment and Off-take at the Top of the Pressurizer in the case of the actuation of Safety Depressurization System of APR1400

No, Hee Cheon; Kim, Chang Hyun, 한국원자력학회 춘계발표회, 한국원자력학회, 2003

143
Liquid entrainment and off-take from the two-phase mixture surface in a vessel

No, Hee Cheon; Kim, CH, NURETH10, 2003

144
Liquid Entrainment and Off-Take Through the Break at the Top of a Vessel

Kim, C.H.; No, Hee Cheon, International Conference on Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment, v.89, pp.426 -, 2003-11-16

145
Local Chemical and Thermal-Hydrai;oc Analysis of U-Tube Steam Generators

No, Hee Cheon; Lee, Jae Young, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operation, 1988

146
Local Heat Transfer Coefficients for Reflux Condensation Experiment in a Vertical Tube in the Presence of Noncondensible Gas

No, Hee Cheon; Moon, Young Min, 한국원자력학회 춘계발표회, 한국원자력학회, 1999

147
Low pressure operation of sulfur-iodine cycle in VHTR through the concept of heat exchanging-pressure depressurizing loop

Kim, Y.S.; No, Hee Cheon; Yoon, H.J.; Lee, JeongIk, 2nd International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management 2010, pp.68 - 74, 2010-06-13

148
Measurement and Model Development of the Droplet Diameter in Rod Bundles with Spacer Grids in the Reactor Core

No Hee Cheon; Lee, Eo Hwak; Shin, Chang Wook; Song, Chul-Hwa, NTHAS7, 2010-11

149
Measurement of droplet size with the freezing droplet method for annular flow in a horizontal pipe

Lee, E.H.; No, Hee Cheon; Song, C.-H., 2007 Winter Meeting on International Conference on Making the Renaissance Real, pp.763 - 764, 2007-11-11

150
Measurement of heat transfer coefficients for direct contact condensation in core makeup tanks using holographic interferometer

No, Hee Cheon; Ju, SH; Mayinger, F, Flow Visualization and Image Processing-1, 1997

151
Measurement of kinetic parameters of nuclear graphite IG-110 for HTGR air-ingress

No, Hee Cheon; Kim, Eung Soo, 한국원자력학회 춘계발표회, 한국원자력학회, 2004

152
Measurement of Temperature Profile Using the Infrared Thermal Camera in Turbulent Stratified Liquid Flow for Estimation of Condensation Heat Transfer Coefficients

No, Hee Cheon; Choi, Sung Won, 한국원자력학회 춘계발표회, 한국원자력학회, 1999

153
Measurement Techniques of Local Parameters in the Downcomer Boiling Experiment of APR1400

No, Hee Cheon; Lee, Eo Hwak; Lee, Dong Won, 한국원자력학회 추계발표회, 한국원자력학회, 2004

154
Measurement techniques of local parameters in the downcorner boiling experiment of APR1400

Lee, E.H.; Lee, B.W.; No, Hee Cheon, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.2, pp.895 - 901, 2005-05-15

155
Measurements of entrained droplet size in a liquid column using a phase Doppler technique

Jeong Hae Yong; No, Hee Cheon; Song, Chul-Hwa; Chung, Moon Ki, Proceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24), v.4, 1997-06-22

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