Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jeong, Yong Hoon
Showing results 54 to 113 of 372
| 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 |
| CFD Simulation of Condensation Heat Transfer in Horizontal Tubes Khasawneh Khalid Walid Mohammad Ali; Jeong, Yong Hoon, The 18th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-18), American Nuclear Society, 2019-08-20 |
| CFD Thermal Analysis over a Narrow Channel for the Investigation of the PCM Solidification Criteria Choi, Yonadan; Jeong, Yong Hoon, 2020 ANS Winter Meeting and Technology Expo, American Nuclear Society, 2020-11-19 |
| CHF correlation development under ERVC conditions by using the local liquid velocity from PIV measurements Yoon, Jongwoong; Kam, Dong Hoon; Park, Hae Min; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.128, pp.171 - 184, 2019-01 |
| CHF correlation development under ERVC conditions in terms of liquid velocity YOON, JONGWOONG; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09-07 |
| CHF Correlation Development under ERVC Conditions Using Local Liquid Velocity YOON, JONGWOONG; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-19 |
| CHF correlation development using local liquid velocity under ERVC conditions = 원자로용기 외벽냉각 조건에서 국부속도를 활용한 임계열유속 상관식 개발link Yoon, Jongwoong; Jeong, Yong Hoon; et al, 한국과학기술원, 2017 |
| 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 |
| CHF enhancement in flow boiling system with TSP and boric acid solutions under atmospheric pressure Lee, Juno; Jeong, Yong Hoon; Shin, Byungsoo; Chang, Soon Heung, Transactions of the Korean Nuclear Society Spring Meeting, pp.737-, 2009-05 |
| CHF Enhancement in Flow Boiling System with TSP and Boric Acid Solutions under Atmospheric Pressure Jeong, Yong Hoon; Lee, Juno; Shin, Byungsoo; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-18 |
| CHF Experiment for Heater Inclination Angle and Material Effect for Downward Facing Surface Jung, Jun Yeong; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-18 |
| CHF experiment with downward-facing carbon and stainless steel plates under pressurized conditions Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.125, pp.670 - 680, 2018-10 |
| 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 |
| 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 |
| CHF for Downward-facing Flat Plates Considering Pressure Up to 2 Bar Condition, Width and Material Effects KAM, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-13 |
| CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions KAM, DONG HOON; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01 |
| CHF Measurement for Downward-Facing Stainless Steel and Carbon Steel Flat Plates under Pool Boiling Condition Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, pp.2054 - 2060, American Nuclear Society, 2016-04-20 |
| 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 |
| CHF model development based on optimal experiments of reactor vessel external cooling = 원자로용기 외벽냉각 임계열유속 최적평가 실험 및 모델 개발link Jung, Jun Yeong; Jeong, Yong Hoon; et al, 한국과학기술원, 2022 |
| CHF of a Downward Curved SA508 Surface with Boric Acid and TSP Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-25 |
| CHF on Anodized Zirconium-based Alloy Surfaces with Protective Oxide Layers for ATF cladding Kam, Dong Hoon; Yu, Hyoung Suk; Jeong, Yong Hoon; Park, Yang Jeong; Kim, Jung Woo; Cho, Sung Oh, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.170, 2021-05 |
| Combined effect of a corrodible material and acidic fluid on flow boiling crisis Jung, Jun Yeong; Lee, Min Suk; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.143, 2023-04 |
| 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 |
| Comparison of decontamination factors from coupled and uncoupled aerosol removal models in rising bubble region under pool scrubbing Kim, YoHan; Kam, Dong Hoon; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants (ICAPP’21), American Nuclear Society (ANS), the Atomic Energy Society of Japan (AESJ), the Korea Nuclear Society (KNS), the French Nuclear Society (SFEN), 2021-10-19 |
| 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 |
| 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 |
| 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 |
| Conceptual design of air curtain application on the reactor vessel auxiliary cooling system (RVACS) = RVACS에 적용 가능한 에어커튼의 개념 설계link Choi, Jaejin; Jeong, Yong Hoon; et al, 한국과학기술원, 2022 |
| Conceptual Design of Decay Heat Passive Cooling System for Spent Fuel Pool with Heat Pipes and Air Cooling Tower: Transient Calculation of Thermal Capacity during both Occasions of Normal and Accident Operation Lee, Min Suk; park, Wooseong; Jeong, Yong Hoon, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Chung-Hwa Nuclear Society, 2022-09-07 |
| 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 |
| Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; Son, In Woo; Kim, Yonghee; Lee, Jeong-Ik; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, 2020-12 |
| Conceptual Design of S-CO2 cooled Micro Modular Reactor for Hybrid Power Generation System (MMR-H) Moon, Jangsik; Choi, Young Jae; Jeong, Yong Hoon, The 6th International Conference on Nuclear and Renewable Energy Resources (NURER2018), Korean Nuclear Society, 2018-10-01 |
| 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 |
| Conceptual Design of Safety Injection Tanks Using the Saturated Water Park, Hae Min; Jeong, Yong Hoon, 2009 Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2009-11 |
| Conceptual design of small modular reactor (SMR) driven by natural circulation and study of design characteristics using CFD Code = 자연순환에 의해 구동되는 소형 모듈형 원자로의 개념설계 및 CFD 코드를 이용한 설계특성 연구link Kim, Mun Soo; Jeong, Yong Hoon; et al, 한국과학기술원, 2020 |
Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code Kim, Mun Soo; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.12, pp.2743 - 2759, 2020-12 |
| 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 |
| Conceptual System Design of a Supercritical CO2 cooled Micro Modular Reactor Kim, Seong Gu; Baik, Seung Joon; Moon, Jangsik; Yu, Hwanyeal; Jeong, Yong Hoon; Kim, Yonghee; Jeong-Ik Lee, ICAPP 2015, American Nuclear Society, 2015-05 |
| 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 |
| Continued Operation and Public Acceptance in Korea Jeong, Yong Hoon; Chang, Soon-Heung, The 27th JAIF-KAIF Seminar on Nuclear Industry, 2005-10-24 |
| Correction factor development for the 2006 Groeneveld CHF look-up table for rectangular channels under low pressure Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, pp.110869, 2020-12 |
| Correction factor development of CHF look-up table for rectangular channel for low pressure Song, Jung Hyun; Lee, Juhyung; Jeong, Yong Hoon, The Eighth China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-8), Korea Atomic Energy Research Institute, Nuclear Power Institute of China, Xi’an Jiaotong University, 2017-10-23 |
| Correction Factor Development of CHF Look-Up Table for Rectangular Channel Under Low Pressure Song, Jung Hyun; Lee, Juhyung; Jeong, Yong Hoon, The 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS11), Korean Nuclear Society, 2018-11-20 |
| Correlations for the Minimum Film Boiling Temperature of Transient Heating and Cooling Process Jeong, Woon Ho; Jeong, Yong Hoon, The 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS11), Korean Nuclear Society, 2018-11-20 |
| 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 |
| Coupled Analysis of Passive Safety Injection and Containment Filtered Venting for Passive Decay Heat Removal Kim, Sang Ho; HAM, JAEHYUN; Chang, Soon-Heung; Jeong, Yong Hoon, 2015 International Congress on Advances in Nuclear Power Plants, American Nuclear Society, 2015-05-06 |
| 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 |
| 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 |
| CRITICAL HEAT FLUX ENHANCEMENT Chang, Soon-Heung; Jeong, Yong Hoon; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11 |
| Critical heat flux enhancement of nuclear fuel cladding with nano-porous oxide film by surface anodization = 표면 양극산화법으로 제조된 나노 다공성 산화막을 가진 핵연료 피복관의 임계열유속 증진link Yu, Hyoung Suk; Jeong, Yong Hoon; et al, 한국과학기술원, 2018 |
| 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 |
| 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 |
| 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 |
| 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 |
| Critical heat flux experiments on the reactor vessel wall using 2-D slice test section Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11 |
| Critical heat flux for SiC- and Cr-coated plates under atmospheric condition Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Tae-Seung; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.76, pp.335 - 342, 2015-02 |
| 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 |
| 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 |
| 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 |
| Critical heat flux model on a downward facing surface for application to the IVR conditions Park, Hae Min; Jeong, Yong Hoon; Carnevali, Sofia, NUCLEAR ENGINEERING AND DESIGN, v.330, pp.317 - 324, 2018-04 |
Discover
Type
- 2,798 Article
- 5,616 Conference
- 430 Patent
- 911 Thesis(Master)
- 546 Thesis(Ph.D)
Open Access
- 152 OA Article
Date issued
- 1,232 2020 - 2024
- 4,359 2010 - 2019
- 2,657 2000 - 2009
- 1,431 1990 - 1999
- 449 1980 - 1989