Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Kam, Dong Hoon
Showing results 1 to 39 of 39
| 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 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 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 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 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 |
| CHF, AGING EFFECT OF SiC SURFACES AND CHF OF Cr SURFACE UNDER ATMOSPHERIC CONDITION WITH SURFACE EVALUATIONS Kam, Dong Hoon; Lee, Jong-Hyuk; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-17 |
| 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 |
| 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 on downward-facing carbon steel flat plates under atmospheric condition Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.90, pp.22 - 27, 2018-01 |
| Depressurization of nuclear power plants through a silica gel-based system Kam, Dong Hoon; Jeong, Yong Hoon; Choi, Sung-Min; Yun, Jong-Il; Lee, Min Suk, NUCLEAR ENGINEERING AND DESIGN, v.381, pp.1111333, 2021-09 |
| Development of analytical model for solar chimney power plant with and without water storage system Choi, Young Jae; Kam, Dong Hoon; Park, Yoon Won; Jeong, Yong Hoon, ENERGY, v.112, pp.200 - 207, 2016-10 |
| Effects of Exit Quality on Flow Boiling CHF Enhancement of Nanofluids Lee, Taeseung; Kam, Dong Hoon; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-24 |
| Effects of silica nanoparticles and low concentration on the deterioration of critical heat flux in a pool boiling experiment with a flat-type heater Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.144, 2019-12 |
| Effects of two-phase flow conditions on flow boiling CHF enhancement of magnetite-water nanofluids Lee, Taeseung; Kam, Dong Hoon; Lee, Jong Hyuk; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.74, pp.278 - 284, 2014-07 |
| Experiment and model development of CHF with consideration of heater surface characteristics and fluid properties = 가열면과 유체의 특성 효과 반영 임계열유속 실험 및 역학적 모델 개발link Kam, Dong Hoon; Jeong, Yong Hoon; et al, 한국과학기술원, 2019 |
| Experiment of CHF Enhancement by Fe3O4 Nanoparticle Coating in Subcooled Boiling Region Choi, Young Jae; Kam, Dong Hoon; Jeong, Yong Hoon, 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, pp.2258 - 2265, American Nuclear Society, 2016-04-20 |
| Experiment Of CHF enhancement by magnetite nanoparticle deposition in the subcooled flow boiling region Choi, Young Jae; Kam, Dong Hoon; Jeong, Yong Hoon, 25th International Conference on Nuclear Engineering, ICONE 2017, American Society of Mechanical Engineers (ASME), 2017-07 |
| Experiment on Pool and Flow Boiling CHF for the SiC Surfaces under Atmospheric Condition Kam, Dong Hoon; Lee, Jong Hyuk; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-25 |
| Experimental evaluations of the critical heat flux in terms of the heater dimensions, orientation, and surface morphology Lee, Min Suk; Jung, Jun Yeong; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.136, 2022-07 |
Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle Choi, Yu Jung; Kam, Dong Hoon; Papadopoulos, Petros; Lind, Terttaliisa; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.6, pp.1756 - 1768, 2021-06 |
| Experimental study on CHF of SiC, Cr surfaces for post fuel cladding in nuclear power plant = 차세대 원자로 SiC, Cr 피복재 표면의 임계열유속에 관한 실험적 연구link Kam, Dong Hoon; 감동훈; et al, 한국과학기술원, 2015 |
| Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors Amidu, Muritala Alade; Addad, Yacine; Lee, Jeong-Ik; Kam, Dong Hoon; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.376, 2021-05 |
| Magnetic withdrawal of particles for multiple purposes in nuclear power plants Kam, Dong Hoon; Jeong, Yong Hoon; Choi, Sung-Min; Yun, Jong-Il, NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.12, pp.3979 - 3989, 2021-12 |
| Measurement of critical heat flux for SiC-coated stainless steel plate and α-SiC tube with short-heated length under atmospheric condition Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, 2014 International Congress on Advances in Nuclear Power Plants, American Nuclear Society, 2014-04-09 |
| Parametic Studies on CHF Trends for a Downward Facing Curved Geometry Under a Flow Condition Jung, Jun Yeong; Kam, Dong Hoon; Park, Hae Min; Jeong, Yong Hoon, The 18th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-18), American Nuclear Society, 2019-08-21 |
| Preliminary assessment of CHF model based on dry patch and heat dissipation concepts using vertical heaters Kam, Dong Hoon; Jeong, Yong Hoon, 2018 ANS annual Meeting, American Nuclear Society, 2018-06-19 |
| Pressurized Environments and Effect of Silica Gel Amount on Depressurization Inside the Containment Kam, Dong Hoon; Jeong, Yong Hoon, The 18th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-18), American Nuclear Society, 2019-08-20 |
| The effect of nanofluid stability on critical heat flux using magnetite-water nanofluids Lee, Jong Hyuk; Kam, Dong Hoon; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.292, pp.187 - 192, 2015-10 |
| The importance of representative aerosol diameter and bubble size distribution in pool scrubbing Kim, Yo Han; Kam, Dong Hoon; Yoon, Jongwoong; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.147, 2020-11 |
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