Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jeong, Yong Hoon
Showing results 1 to 60 of 370
| A Case Study of Risk Informed Asset Management (RIAM) for Nuclear Power Plant Lee,Gyoung Cheol; Jeong, Yong Hoon; Chang, Soon-Heung; Chung, Dae-Wook, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-02 |
| A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region Kim, Seong Gu; Yu, HwanYeal; Moon, Jangsik; Baik, Seungjoon; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong-Ik, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.41, no.4, pp.512 - 525, 2017-03 |
| A conceptual study of air curtain on the reactor vessel auxiliary cooling system Choi, Jaejin; Jeong, Yong Hoon, 2022 ANS Annual Meeting, American Nuclear Society, 2022-06-15 |
| A critical heat flux model for flow boiling in the IVR conditions Park, Hae Min; Carnevali, Sofia; Gaudier, Fabrice; Jeong, Yong Hoon, 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017, International Congress on Advances in Nuclear Power Plants, ICAPP, 2017-04 |
| A feasibility study of application in NPPs using magnetite-water nanofluid Lee, Jong Hyuk; Kam, Dong Hoon; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| A heat transfer model development for CHF prediction with consideration of dry patch characteristics Kam, Dong Hoon; Jeong, Yong Hoon; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.148, 2020-02 |
| A Mechanistic Model of Onset of Flow Instability Due to Mergence of Bubble Layers in a Vertical Narrow Rectangular Channel Lee, Juhyung; Jeong, Yong Hoon; Chang, Soon Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-12 |
| A new design concept for offshore nuclear power plants with enhanced safety features Lee, Kihwan; Lee, Kang-Heon; Lee, JeongIk; Jeong, Yong Hoon; Lee, Phill-Seung, NUCLEAR ENGINEERING AND DESIGN, v.254, pp.129 - 141, 2013-01 |
| A novel approach for critical heat flux enhancement during severe accident mitigation with removal of radioactive materials from the coolant Kam, Dong Hoon; Jeong, Yong Hoon; Choi, Sung-Min; Yun, Jong-Il; Lee, Jong Hyuk; Lee, Taeseung; Lee, Min Suk; et al, NUCLEAR ENGINEERING AND DESIGN, v.365, pp.110715 - 110725, 2020-08 |
| A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA Kim, Sang Ho; Chang, Soon Heung; Choi, Yu Jung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.295, pp.346 - 359, 2015-12 |
| A Preliminary Experimental Study of Filmwise and Dropwise Condensation on SUS316 Surface Choi, Jae Young; Jeong, Yong Hoon; Watanabe, Noriyuki, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2015-10-30 |
| A study of the behavior of the floating absorber for safety at transient(FAST) in an innovative sodium-cooled fast reactor (iSFR) Lee, Seongmin; Kim, Yonghee; Choi, Yonadan; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.179, 2022-12 |
| A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel Choi, Gil Sik; Jeong, Yong Hoon; Chang, Soon Heung, NUCLEAR ENGINEERING AND DESIGN, v.294, pp.103 - 116, 2015-12 |
| A Study on the Correlations Development for Film boiling Heat Transfer on Spheres Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1998-05-01 |
| A Study on the Development of On-Line Source Term Estimation System for PWRs Kim, TW; Jeong, Yong Hoon; Choi, SS; Cho, GW; Shin, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
| A Study on the Non-Heating CHF Experiments Using Drilled Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1999-05-28 |
| A Study on the Non-Heating Simulation ofPool Boiling CHF on Flat Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000-10-26 |
| A study on the pool scrubbing removal efficiency by droplets in the submerged gas jet Kim, Yo Han; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants (ICAPP’23), American Nuclear Society (ANS), the Korea Nuclear Society (KNS), 2023-04-24 |
| (A) conceptual safety and security integrated design methodology for nuclear power plant = 원자력 발전소의 안전과 보안 통합 개념 설계 방법론link Joung, Sung Yeop; 정성엽; Jeong, Yong Hoon; 정용훈; et al, 한국과학기술원, 2014 |
| (A) study of the behavior of the floating absorber for safety at transient (FAST) to improve inherent safety of a sodium-cooled fast reactor and multi-assembly-based design optimization = 고속로 고유 안전성 향상을 위한 피동안전흡수체의 거동 연구 및 다중 어셈블리 기반 설계 최적화link Lee, Seongmin; Jeong, Yong Hoon; et al, 한국과학기술원, 2022 |
| (A) study on analysis methodology for dynamic characteristics of check valves in nuclear power plant using CFD = 전산유체역학을 활용한 원자력발전소 역지밸브의 동적특성 분석 방법론에 관한 연구link Kim, Namseok; Jeong, Yong Hoon; et al, 한국과학기술원, 2021 |
| (A) Study on DNBR evaluation method by grouping of axial power distribution = 축방향 출력분포의 그룹핑을 통한 핵비등이탈률 평가 방법 연구link Kim, Sung Min; Jeong, Yong Hoon; et al, 한국과학기술원, 2021 |
| (A) study on the fire retardant performance of non-class 1E cables depending on the ambient temperature condition surrounding the facilities for flame test of cables = 케이블 화염시험 설비 주위 온도 조건에 따른 비안전등급 케이블 난연성능 변화에 대한 연구link Moon, Young-Seob; Jeong, Yong Hoon; et al, 한국과학기술원, 2020 |
| (A) study on the onset of flow instability and critical heat flux in a narrow rectangular channel = 좁은 사각채널에서의 유동불안정개시 및 임계열유속에 관한 연구link Lee, Juhyung; 이주형; et al, 한국과학기술원, 2016 |
| Air-water Flow Measurement for ERVC Conditions by LIF/PIV Yoon, Jongwoong; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-13 |
| An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs Park, Jae Hong; Jeong, Yong Hoon; Baek, Won Pil; Chang, Soon Heung, ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250, 2001-08 |
| AN AXIOMATIC DESIGN APPROACH OF NANOFLUID-ENGINEERED NUCLEAR SAFETY FEATURES FOR GENERATION III plus REACTORS Bang, In Cheol; Heo, Gyunyoung; Jeong, Yong Hoon; Heo, Sun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.9, pp.1157 - 1170, 2009-11 |
| An axiomatic design approach of nanofluid-engineered nuclear safety features for generation III+ reactors Bang, I.C.; Heo, G.; Jeong, Yong Hoon; 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 |
| An experimental observation of the effects of submicron- and micron-sized mesoporous silica particles on the critical heat flux Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.160, pp.120182, 2020-10 |
| 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 Heung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| An Experimental study on the onset of nucleate boiling in narrow rectangular channel for downward flow = 저압 조건 아래 좁은 사각 채널, 하향 유동에서의 핵비등 개시에 대한 실험적 연구link Song, Jung Hyun; 송중현; et al, 한국과학기술원, 2015 |
| An Experimental Study on the Onset of Nucleate Boiling in Rectangular Channels for Downward Flow Song, Jung Hyun; Lee, Juhyung; Chang, Soon-Heung; Jeong, Yong Hoon, 2015 ANS Annual Meeting (Summer), American Nuclear Society, 2015-06-09 |
| ANALYSIS CODE DEVELOPMENT FOR THE BEHAVIOR OF FLOATING ABSORBER FOR SAFETY AT TRANSIENT IN INNOVATIVE SODIUM-COOLED FAST REACTOR Lee, SeongMin; 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, 2017-10-24 |
| Analysis of CHF enhancement by magnetite nanoparticle coating in subcooled boiling region Choi, Young Jae; KAM, DONG HOON; 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 |
| Analysis of CHF enhancement by magnetite nanoparticle deposition in the subcooled flow boiling region Choi, Young Jae; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.109, pp.1191 - 1199, 2017-06 |
| Analysis of CHF Enhancement in Subcooled Flow Boiling Experiment Choi, Young Jae; KAM, Dong Hoon; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-12 |
| Analysis of Flow Instabilities in Multi-channel Loop Type Thermosyphon You, Byung-Hyun; Jeong, Yong Hoon, 2014 22nd International Conference on Nuclear Engineering (ICONE22), ASME, 2014-07-11 |
| Analysis of Hydrogen Economy using Vensim Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28 |
| Analysis of Supercritical CO2 Brayton Cycles for Pertinent Compressor Inlet Conditions Jeong, Woo Seok; Jeong, Yong Hoon, 2012 ANS Annual Meeting, American Nuclear Society, 2012-06-27 |
| Analysis of the Nitrogen Entrainment in a Safety Injection Tank with a Small Scaled Experiment Jeong, Woon Ho; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-19 |
| Analysis of the QUENCH-06 experiment with the integrated severe accident analysis code CINEMA Jeong, Woon Ho; Jeong, Yong Hoon, The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS12), Atomic Energy Society of Japan, 2022-10-31 |
| Analysis of World Nuclear Market and Strategy of Korean NPP’s Competitiveness Improvement for Exportation Choi, Jae Young; Roh, Seungkook; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27 |
| Analysis on Fission Products Diffusion using Finite Difference Method Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10 |
| Application of computational fluid dynamics codes for nuclear reactor design You, Byung-Hyun; Moon, Jangsik; Jeong, Yong Hoon, International Electronic Journal of Nuclear Safety and Simulation, v.6, no.3, pp.226 - 233, 2015-09 |
| Application of multi-functional nanoparticle to nuclear power plant during severe accident or decontamination process using its magnetic property KAM, DONG HOON; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09-08 |
| Application of ordinary Kriging interpolation for 3-D power distribution synthesis in core protection calculator = 노심보호연산기의 3차원 출력분포 합성을 위한 정규 크리깅 보간법 적용link Kwon, Young Min; Jeong, Yong Hoon; et al, 한국과학기술원, 2023 |
| Assessment of advanced RANS models ability to predict a turbulent swept liquid metal flow over a wire in a channel You, Byung-Hyun; Jeong, Yong Hoon; Addad, Yacine, NUCLEAR ENGINEERING AND DESIGN, v.353, 2019-11 |
| Assessment of critical heat flux (chf) performance in water using sic-coated plate and -sic pipe under atmospheric pressure Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Tae-Seung; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1693 - 1700, Korean Nuclear Society, 2013-04-18 |
| Assessment of Dryout Heat Flux Correlations for Particle Beds Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01 |
| Assessment of pool boiling CHF enhancement using magnetite and alumina water nanofluids at higher pressure Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10 |
| Assessment of two-equation and second-moment closures for flow and energy predictions in wire-wrapped sub-channel of liquid metal reactor using unstructured finite volume codes = 비정렬 유한 체적 코드를 활용한 2-방정식 및 2차 모멘트 닫힘 난류모델의 액체금속로 부수로 내 유동 및 에너지 예측 평가link You, Byung-Hyun; 유병현; et al, 한국과학기술원, 2017 |
| BA, Dissolved Metal Effects Regarding CHF on Vertical SS304 & SA508 Flat Plates under Pool Boiling and Atmospheric Conditions Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), Thermal Hydraulics Divisions of AESJ, KNS, 2016-11-29 |
| Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.136, 2020-02 |
| 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 |
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