NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 3061 to 3080 of 5619

3061
A Quantitative Assessment Method for Trip Signal Generation Failures

신승기; 성풍현, 한국원자력학회 2010 춘계학술발표대회, 한국원자력학회, 2010-05-28

3062
Performance of S-CO2 Brayton Cycle with Additive Gases for SFR Application

Jeong, Woo Seok; Jeong, Yong Hoon; Lee, Jeong Ik, Supercritical CO2 Power Cycle Symposium, 2011-05-25

3063
PIMA: RFID and USN based personalized indoor microclimate adjuster

Chang, Seong Ju; Kim C.; Suh D., International Conference on Control, Automation and Systems, ICCAS 2010, pp.859 - 862, 2010-10-27

3064
Potential Improvements of Supercritical Recompression CO2 Brayton Cycle Coupled with KALIMER-600 by Modifying Critical Point of CO2

Jeong, Woo Seok; Lee, Jeong Ik; Jeong, Yong Hoon; NO, Hee Cheon, Korean Nuclear Society Autumn Meeting, 2010-10-21

3065
Experimental Investigation on the CHF Enhancement of Pool Boiling using Magnetic Fluid

Lee, Jong Hyuk; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21

3066
A New Correlation for Counter-Current Flow Limited CHF in Narrow Rectangular Channels

Lee, Ju Hyung; Chang, Soon-Heung, 한국원자력학회 춘계학술발표회, 한국원자력학회, 2011-05-26

3067
Conservative Estimation of In-Vessel Retention for High Power Reactors

Kim, Sang Ho; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21

3068
Flow Boiling CHF Experiments using Nanofluid under Different Heating Rate

Kim, TI; Jee, YT; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2011-05-26

3069
Effect of application SiC fuel cladding for mitigating focusing effect in situation of IVR

Song, Sub Lee; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21

3070
Linear Programming Optimization of Nuclear fuel cycle in Korea

Lee, J.; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21

3071
Cost comparison of direct disposal vs. pyro-processing and DUPIC in Korea

Lee, J.; Chang, Soon-Heung, 한국원자력학회 춘계학술대회, 한국원자력학회, 2010-05-27

3072
CHF Experiments under Realistic Severe Accident Condition for IVR-ERVC Strategy

Kim, TI; Park, HM; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21

3073
Evaluation of Communication Quality using Work Domain Analysis (WDA) Method in Nuclear Power Plant Control Rooms

장인석; 박진균; 성풍현, 한국원자력학회 2010 춘계학술발표대회, 한국원자력학회, 2010-05-27

3074
Incorporation of materials’ sensitive simulation technique into the PINTIN-CAM code for integrity of nuclear piping system

Jang, Changheui, Pressure Vessels & Piping 2010, 2010-07-20

3075
Integrity of Ni-base superalloys for advanced nuclear systems application - environment and materials interaction

Jang, Changheui; Kim, D; Kim, D; Kim, M; Sah, I; Ryu, WS; Yoon, DJ, Structural Materials for Innovative Nuclear System (SMINS)-2, 2010-09-01

3076
Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments

Jang, Changheui, IUMRS 11th International Conference in Asia, 2010-09-28

3077
The Effects of Dissolved Hydrogen Contents on the Low Cycle Fatigue Behaviors of a 316LN Stainless Steel in Simulated PWR Condition

Jang, Changheui; Cho, Pyung-Yeon; Hong, Jong-Dae; Jang, Hun; Kim, Tae-Soon; Lee, Jae-Gon, Nuclear Plant Chemistry Conference 2010, 2010-10-05

3078
Diametral creep prediction of pressure tube using statistical regression methods

Kim, D.; Lee, J.Y.; Na, M.G.; Jang, Changheui, 31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010, pp.514 - 520, 2010-05-24

3079
Effects of Material Variability and Dissolved Hydrogen Content on LCF of 316LN

Jang, Changheui, ICG-EAC 2010, 2010-04-13

3080
Development of a HRA method based on human factor issues for advanced NPP

Lee, S.W.; Ha, J.S.; Seong, Poong-Hyun, 7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010, pp.1462 - 1474, 2010-11-07

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