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

Showing results 18 to 77 of 116

18
CFD Analysis of Dry Storage System for CANDU Spent Fuel using Fluent 6.2

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

19
CHF Enhancement in Flow Boiling at low mass flux using Al2O3 Nano-fluid

Kim, Tae Il; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05

20
CHF Experiments for IVR-EVC using 2-D Slice Test Section

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

21
CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section

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

22
CHF Measurement for Flat Plates Considering Dimensional Effects (Length & Width) under Atmospheric and Pool Boiling Conditions

KAM, DONG HOON; Choi, Young Jae; Jeong, Yong Hoon; 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

23
Comparative Study on the Power Generation Options in Korea using Multi Criteria Decision Analysis

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

24
Conceptual Design of a Nuclear Reactor Dedicated for Desalination

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

25
Conceptual Design of a Nuclear Reactor for Desalination

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

26
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 Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10-25

27
Conceptual Design of NaN3 Inflator for Safety Injection Tanks

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

28
Conceptual Design of Safety Injection Tanks Using Saturated Water

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

29
Conceptual Design of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination

Jeong, Woonho; 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

30
Condensation Experiment for a Desalination System Using the Waste Heat of Nuclear Power Plants and Solar Energy Systems

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

31
Continued Operation and Public Acceptance in Korea

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

32
Cost-benefit Analysis Based on PSA for Additional Passive Safety System and Alternative AC Power Source

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

33
Critical heat flux characteristic of magnetite-water nanofluid in pool boiling

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

34
Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions

Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11

35
Critical Heat Flux Enhancement: Nano-fluids and Others

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

36
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 Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21

37
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 Hoon, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12

38
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 Hoon, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17

39
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 Hoon, 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

40
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 Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

41
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 Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-03

42
Design of Graphic Aggregation Model for Evaluation of Energy Systems

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

43
Design of Nuclear Power Plant Online Monitoring System

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

44
Design of Safety Injection Tanks Using Axiomatic Design and TRIZ

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

45
Development of nuclear power plant online monitoring system using statistical quality control

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

46
Effect of Geometry, Heater Material and Coolant Additives on CHF of Curved Inclined Surface

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

47
Effect of Magnetite Nanoparticle Deposition Kinetics on the Flow Boiling CHF Characteristics of Magnetite-Water Nanofluid

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

48
Effects of Magnetic Field on Flow Boiling CHF in Fe3O4 Ferrofluid

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

49
Effects of Magnetic Field on Flow Boiling CHF in Magnetite-water Nanofluid

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

50
Effects of Magnetic Fields on the Flow Boiling CHF of Magnetic Nanofluids

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

51
Estimation of Fission Product Release from the TRISO Fuel

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

52
Estimation of fission product release from TRISO

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

53
Estimation ofthe Thermal Efficiency of Hybrid Sulfur Cycle for Hydrogen Generation using Gas Cooled Reactor

Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27

54
Evaluation of Heat Removal Performance of Passive Decay Heat Removal system for S-CO2 Cooled Micro Modular Reactor

Moon, Jangsik; Lee, Jeong-Ik; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2015-05-08

55
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

56
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

57
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

58
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

59
Experimental CHF Study on the Pressure Effect in the 2-D Slice Test Section

Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-30

60
Experimental CHf study on the scaling effect of 2-D slice test section for in-vessel retention through external reactor vessel cooling strategy

Park, Hae Min; Heo, Sun; Song, Chanyi; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02

61
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

62
Experimental Simulation of Partial Uncovery during LOCA in Spent Fuel Pool

KIM, Yong Jin; Jeong, Yong Hoon; Moon, Sang Ki, International Workshop on Nuclear Safety and Severe Accident(NUSSA (Embedded to NUTHOS-11)), Korean Nuclear Society and American Nuclear Society, 2016-10-12

63
Experimental Study on the Critical Heat Flux Characteristic of the Seawater

Park, Hae Min; Lee, Taeseung; Jeong, Yong Hoon, The 18th Pacific Basin Nuclear Conference(PBNC 2012), KAIF,KNS, 2012-05

64
Experimental study on the pool boiling CHF Enhancement Using Magnetic Fluid

Lee, Jong Hyuk; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25

65
Feasibility of Using Magnetic Nanofluid for Enhanced Cooling Capability

Lee, Taeseung; Lee, Jong Hyuk; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2012-09

66
Fission Product Release from TRISO by Diffusion

Chang, Won Joon; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-27

67
Flow Boiling CHF Enhancement using Porous Surface Coatings

Sawar, M. Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-26

68
Flow Boiling Critical Heat Flux Enhancement by Using Magnetic Nanofluids and External Magnetic Fields

Lee, Taeseung; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25

69
Flow boiling critical heat flux enhancement on the 2-D slice for boric acid and TSP solution

Park, Hae Min; Heo, Sun; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25

70
Flow Boiling Critical Heat Flux Enhancement with Tri-Sodium Phosphate and Boric Acid Solution in the Tube

Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10

71
Flow Measurement in a 2-D Slice for ERVC Conditions by PIV

Yoon, Jongwoong; 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

72
Flow sheet analysis of nuclear hydrogen production from water and sulfur

Jung, Yong Hun; Jeong, Yong Hoon, 2nd International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management 2010, pp.83 - 89, 2010-06-13

73
Fuel Options for Vehicles in Korea and Role of Nuclear Energy

Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28

74
Growth of Bubble layer and Onset of Flow Instability in a vertical Narrow rectangular channel

이주형; 장순흥; 정용훈, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2015-05-08

75
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

76
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

77
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

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