Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 1381

Showing results 1 to 60 of 139

1
A Case Study of Risk Informed Asset Management (RIAM) for Nuclear Power Plant

Lee,Gyoung Cheol; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher; Chung, Dae-Wook, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-02

2
A feasibility study of application in NPPs using magnetite-water nanofluid

Lee, Jong Hyuk; Kam, Dong Hoon; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

3
A Methodology for Assessment of External Vessel Cooling During Severe Accidents in PWRs

Park, Jae Hong; Baek, Won Pil; Jeong Yong Hoonresearcher; Chang, Soon-Heungresearcher, Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS2), v.Volume 1, pp.494 - 500, 2000-10-15

4
A Parametric Study for Designing Capacitive Deionization System

Lee Taeseung; Lee, JeongIkresearcher; Jeong Yong Hoonresearcher, 2010 Australia's International Water Conference and Exhibition (OZWATER '10), Australian Water Association, 2010-03-08

5
A Study on the Correlations Development for Film boiling Heat Transfer on Spheres

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1998-05-01

6
A Study on the Development of On-Line Source Term Estimation System for PWRs

Kim, TW; Jeong, Yong Hoonresearcher; Choi, SS; Cho, GW; Shin, HG; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24

7
A Study on the Non-Heating CHF Experiments Using Drilled Plates

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1999-05-28

8
A Study on the Non-Heating Simulation ofPool Boiling CHF on Flat Plates

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000-10-26

9
An assessment methodology for in-vessel cerium retention by external reactor vessel cooling during severe accidents in PWRs

Park, Jae Hong; Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon Heung, ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250, 2001-08

10
An axiomatic design approach of nanofluid-engineered nuclear safety features for generation III+ reactors

Bang, I.C.; Heo, G.; Jeong, Yong Hoonresearcher; Heo, S., The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), v.41, pp.1157 - 1170, NUTHOS, 2008-10-05

11
An Experimental Study on the Convective Heat Transfer in Narrow Rectangular Channels for Downward Flow to Predict Onset of Nucleate Boiling

Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heungresearcher; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

12
An Experimental Study on the Onset of Nucleate Boiling in Rectangular Channels for Downward Flow

Song, Jung Hyun; Lee, Juhyung; Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, 2015 ANS Annual Meeting (Summer), American Nuclear Society, 2015-06-09

13
Analysis of CHF enhancement by magnetite nanoparticle coating in subcooled boiling region

Choi, Young Jae; KAM, DONG HOON; Jeong, Yong Hoonresearcher, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-11

14
Analysis of Flow Instabilities in Multi-channel Loop Type Thermosyphon

You, Byung-Hyun; Jeong, Yong Hoonresearcher, 2014 22nd International Conference on Nuclear Engineering (ICONE22), ASME, 2014-07-11

15
Analysis of Hydrogen Economy using Vensim

Jun, Eunju; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28

16
Analysis of Supercritical CO2 Brayton Cycles for Pertinent Compressor Inlet Conditions

Jeong, Woo Seok; Jeong, Yong Hoonresearcher, 2012 ANS Annual Meeting, American Nuclear Society, 2012-06-27

17
Analysis of World Nuclear Market and Strategy of Korean NPP’s Competitiveness Improvement for Exportation

Choi, Jae Young; Roh, Seungkook; Chang, Soon Heungresearcher; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27

18
Analysis on Fission Products Diffusion using Finite Difference Method

Jeong, Hyedong; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10

19
Assessment of Dryout Heat Flux Correlations for Particle Beds

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01

20
Assessment of pool boiling CHF enhancement using magnetite and alumina water nanofluids at higher pressure

Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, KNS, 2012-10

21
CFD Analysis of Dry Storage System for CANDU Spent Fuel using Fluent 6.2

Shin, Byungsoo; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25

22
CHF Enhancement in Flow Boiling at low mass flux using Al2O3 Nano-fluid

Kim, Tae Il; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05

23
CHF Enhancement in Flow Boiling System with TSP and Boric Acid Solutions under Atmospheric Pressure

Jeong, Yong Hoonresearcher; Lee, Juno; Shin, Byungsoo; Chang, Soon-Heungresearcher, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-18

24
CHF Experiments for IVR-EVC using 2-D Slice Test Section

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2002-05-23

25
CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section

Jeong, Yong Hoonresearcher; Baek, Won-Pil; Chang, Soon-Heungresearcher, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10-05

26
CHF Measurement for Flat Plates Considering Dimensional Effects (Length & Width) under Atmospheric and Pool Boiling Conditions

KAM, DONG HOON; Choi, Young Jae; Jeong, Yong Hoonresearcher; Park, Hae Min, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-10

27
Comparative Study on the Power Generation Options in Korea using Multi Criteria Decision Analysis

Jun, Eunju; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27

28
Conceptual Design of a Nuclear Reactor Dedicated for Desalination

Jung, Yong Hun; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

29
Conceptual Design of a Nuclear Reactor for Desalination

Jung, Yong Hun; Moon, Jangsik; Jeong, Yong Hoonresearcher, The 29th KAIF/KNS Annual Conference, KAIF/KNS, 2014-04-17

30
Conceptual Design of Additional Injection Tank for Heat Load Reduction on Reactor Vessel Lower Head during Severe Accident

Hu, Ji Young; Park, Hae Min; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, KNS, 2012-10-25

31
Conceptual Design of NaN3 Inflator for Safety Injection Tanks

Heo, Gyunyoung; Jeong, Yong Hoonresearcher; Kim, Tae Mi, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2007-10-26

32
Conceptual Design of Safety Injection Tanks Using Saturated Water

Park, Hae Min; Jeong, Yong Hoonresearcher; Chang, Won Joon, The Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4), WORTH, 2009-05

33
Conceptual Design of Safety Injection Tanks Using the Saturated Water

Park, Hae Min; Jeong, Yong Hoonresearcher, 2009 Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2009-11

34
Conceptual Design of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination

Jeong, Woonho; Jeong, Yong Hoonresearcher, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-12

35
Condensation Experiment for a Desalination System Using the Waste Heat of Nuclear Power Plants and Solar Energy Systems

Khasawneh, Khalid; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27

36
Continued Operation and Public Acceptance in Korea

Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, The 27th JAIF-KAIF Seminar on Nuclear Industry, 2005-10-24

37
Cost-benefit Analysis Based on PSA for Additional Passive Safety System and Alternative AC Power Source

Kim, Sang Ho; Kang, Hyun Gookresearcher; Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-04

38
Critical heat flux characteristic of magnetite-water nanofluid in pool boiling

Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Thermal Hydraulics Divisions of AESJ, KNS, 2012-12

39
Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions

Sarwar, Mohammad Sohail; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11

40
Critical Heat Flux Enhancement: Nano-fluids and Others

Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics, 2008-01-07

41
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, 2010-10-21

42
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12

43
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17

44
Critical Heat Flux Measurement for downward facing flat plates (SUS 304, SA 508) under atmospheric and pool boiling conditions

Kam, Dong Hoon; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoonresearcher, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-7), Nuclear Power Institute of China, Korea Atomic Energy Research Institute, 2015-10-15

45
Critical Heat Flux Measurement of SiC- and Cr-coated Plates, Bare Stainless Steel Plate and Zircaloy-4 Plate Under Atmospheric and Pool Boiling Conditions

Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

46
Critical Heat Flux Measurement of SiC- and Cr-coated surfaces with reference surfaces for pool boiling and α-SiC tube for flow boiling under atmospheric conditions, Surface change of SiC-coated surface

Kam, Dong Hoon; Jeong, Yong Hoonresearcher, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-03

47
Demonstration of Gas Circulation Loop Operation in the DTHT Regime

Lee, Jeong Ik; No, Hee Cheon; Jeong, Yong Hoonresearcher, 2009 Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2009-11-15

48
Design of Graphic Aggregation Model for Evaluation of Energy Systems

An, Sang Ha; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25

49
Design of Nuclear Power Plant Online Monitoring System

An, Sang-ha; Lee, Song-kyu; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10

50
Design of Safety Injection Tanks Using Axiomatic Design and TRIZ

Heo, Gynu Young; Jeong, Yong Hoonresearcher, 5th International Youth in Nuclear Congress, 2008-09-20

51
Development of Dedicated Nuclear Heat Only Desalination System for UAE

Jung, Yong Hun; Jeong, Yong Hoonresearcher, 2012 ANS Winter Meeting and Nuclear Technology Expo Embedded Topical Meeting, American Nuclear Society, 2012-11

52
Development of nuclear power plant online monitoring system using statistical quality control

An, Sang Ha; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, 2006 Winter Meeting of the American Nuclear Society, pp.932 - 934, American Nuclear Society, 2006-11-12

53
Effect of Geometry, Heater Material and Coolant Additives on CHF of Curved Inclined Surface

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

54
Effect of Magnetite Nanoparticle Deposition Kinetics on the Flow Boiling CHF Characteristics of Magnetite-Water Nanofluid

Lee, Taeseung; Lee, Jong Hyuk; Jeong, Yong Hoonresearcher, The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), KNS,CNS, 2011-10-10

55
Effects of Magnetic Field on Flow Boiling CHF in Fe3O4 Ferrofluid

Lee, Taeseung; Park, Hae Min; Lee, Jong Hyuk; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, 2010-10-21

56
Effects of Magnetic Field on Flow Boiling CHF in Magnetite-water Nanofluid

Lee, Taeseung; Lee, Jong Hyuk; Park, Hae Miin; Jeong, Yong Hoonresearcher, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESF,ANS,KNS, 2011-05-02

57
Effects of Magnetic Fields on the Flow Boiling CHF of Magnetic Nanofluids

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

58
Estimation of Fission Product Release from the TRISO Fuel

Jeong, Hyedong; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25

59
Estimation of fission product release from TRISO

Jeong, Hyedong; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, 2006 Winter Meeting of the American Nuclear Society, pp.858 - 859, American Nuclear Society, 2006-11-12

60
Estimation ofthe Thermal Efficiency of Hybrid Sulfur Cycle for Hydrogen Generation using Gas Cooled Reactor

Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27

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