Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference
Showing results 3901 to 3960 of 5616
| Preliminary Study on effects of ESS integrated nuclear power plants with increased penetration of renewable energy 조재완; 이정익, 한국원자력학회 2020춘계학술발표회, 한국원자력학회, 2020-05-21 |
| Preliminary Study on Optimization for S-CO2 Cycle coupled to ATOM Reactor 백정열; 이정익, 2018 한국원자력학회 추계학술발표회, 한국원자력학회, 2018-10-25 |
| Preliminary Study on Passive Cooling of Instrumentation and Control Room Using PCMs 조재완; 이정익, 한국원자력학회 2021 춘계학술발표회, 한국원자력학회, 2021-05-13 |
| Preliminary study on reduction of cartoon artifact in the iteratively reconstructed images from sparse projection views Wi, Sunhee; Cho, Seungryong; Abbas, Sajid, World Congress Medical Physics and Biomedical Engineering, WC2015, 2015-06-11 |
| Preliminary Study on S-CO2 Leakage to High Pressure Water 이재준; 이정익, 2020 한국원자력학회 추계학술대회, 한국원자력학회, 2020-12-18 |
| Preliminary Study on Tank Design for S-CO2 Power Cycle Inventory Control 이재준; 오봉성; 백정열; 이정익, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-24 |
| Preliminary Study on the Concept of Boiling Condensing Reactor for Natural Circulation PWR Type SMR 백정열; 채용재; 이정익, 2020 한국원자력학회 추계학술발표회, 한국원자력학회, 2020-12-18 |
| Preliminary Study on the Effect of Pressure Drop due to Spacer Grid in SMRs Jung, Hwa Young; Kim, Min Gil; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05 |
| Preliminary Test of Friction disk type turbine for S-CO2 cycle application 백승준; 김현태; 이정익, 2016 한국원자력학회 춘계학술발표회, 한국원자력학회, 2016-05-13 |
| Preliminary Test of Friction disk type turbine for S-CO2 cycle application Baik, Seungjoon; Kim, Hyeon Tae; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting, The Korean Nuclear Society, 2016-05-12 |
| Preliminary test of friction disk type turbine for small size S-CO2 cycle application Baik, Seungjoon; Heo, Jin Young; Cho, Seong Kuk; Lee, Jeong-Ik, American Nuclear Society (ANS) Winter Meeting(2016), American Nuclear Society, 2016-11-06 |
| Preliminary Test Results of Supercritical CO2 Brayton Cycle Integral Experiment Loop (SCIEL) Cho, Seong Kuk; Lee, Jekyoung; Lee, Jeong-Ik; Cha, Jae Eun; Kim, Tae Ho, 9th National Congress on Fluids Engineering, 한국가시화정보학회, 2016-08-10 |
| Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application 남승현; 이정익; 장순흥, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-30 |
| Preliminary Thermohydraulic Analysis of a New Moderated Reactor Utilizing a LEU-Fuel for Space Nuclear Thermal Propulsion Nam, Seung Hyun; Choi, Jae Young; Venneri, Paolo; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2015-10-30 |
| Preliminary Validation and Verification of TURBO_DESIGN for S-CO2 Axial Compressor Lee, Jekyoung; Lee, JeongIk; Ahn, Yoonhan; Kim, Seong Gu; Yoon, Ho Joon; Yacine Addad, Transactions of the Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2012-05 |
| Premature and Stable Critical Heat Flux for Downward Flow in a Narrow Rectangular Channel Lee, Juhyung; Jo, Dae Seong; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| Preparation of Cesium (Cs) Release Test for Verifying Diffusion Coefficient in the IG-110 Graphite Matrix Baek, Je Kyun; Ryu, Ho Jin; Yeo, Sung Hwan; Lee, Young Woo; Lee, Jeong Mook, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27 |
| Preparedness of Operation Teams' non-technical Skills in a Main Control Room of Nuclear Power Plants to Manage Emergency Situations 임호빈; 김아름; 성풍현, 한국원자력학회 2012 춘계학술발표대회, 한국원자력학회, 2012-05-18 |
| Present and Future of Safety Analysis Codes for High Temperature Gas-Cooled Reactors No, Hee Cheon, NUTHOS-7 Keynote lecture |
| Present Status of High Strength Low Ally Steels 김인섭, Steel Industry Seminar, The Korea Iron and Steel Association, 1981 |
| Pressure and Magnetic Field Effects on CHF of Magnetic Nanofluids Lee, Taeseung; Jeong, Yong Hoon, 2012 ANS Winter Meeting and Nuclear Technology Expo Embedded Topical Meeting, American Nuclear Society, 2012-11 |
| Pressure Calculation of Intergranular Bubbles in UO2 김재준; 류호진, 2021 한국원자력학회 온라인 춘계학술발표회, 한국원자력학회, 2021-05-13 |
| Pressure effect on critical heat flux on the wire in pool of water based nanofluids with alumina and magnetite nanoparticles 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 |
| Pressure Effect on Pool Boiling Critical Heat Flux in Water-based Nanofluids with Alumina and Magnetite Nanoparticles Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-15), N.IN.E, 2013-05-13 |
| Pressure Ratio and Enthalpy Rise as Performance Indicators for S-CO2 Compressor based on Similitude 정용주; 손성민; 조성국; 이정익, 2020 한국원자력학회 추계 학술발표회, 한국원자력학회, 2020-12-17 |
| 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 |
| Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant Jang, Changheui, PVP 2000, 2000-07-24 |
| Principles of Small Angle Neutron Scattering 최성민, HANARO Cold Neutron School, HANARO Cold Neutron School, 2015-08 |
| Principles of Small Angle Neutron Scattering 최성민, 7th PLS-II Summer School, 포항가속기연구소, 2015-07-28 |
| Principles of Small Angle Neutron Scattering 최성민, The Cold Neutron Summer School 2012, 한국원자력연구원, 2012-07 |
| Principles of Small Angle X-ray Scattering 최성민, The 4th PLS-II Summer School and Tutorials, 포항가속기연구소, 2012-07 |
| Printed circuit heat exchanger design and performance analysis near the CO2 critical point for S-CO2 power cycle applications Baik, Seungjoon; Kim, Seong Gu; Song, SeongMin; Kim, Hyeon Tae; Lee, Jeong-Ik, The First Pacific Rim Thermal Engineering Conference(2016), American Society of Thermal and Fluids Engineers, 2016-03-13 |
| Printed Circuit Heat Exchanger Design, Analysis and Experiment Baik, Seung Joon; Kim, Seong Gu; Son, Seong Min; Lee, Jeong Ik, NURETH-16 (2015), ANS, 2015-09-03 |
| Priority queue with two state Markov modulated arrivals Choi Bong Dae; Shin, Byung-Cheol; Choi Ki Bong; Han Dong Hwan; Jang Jae Shin, Proceedings of the 1996 IEEE International Conference on Communications, ICC'96. Part 1 (of 3), v.2, pp.1055 - 1059, 1996-06-23 |
| Probabilistic fracture mechanics application for Alloy 600 components in PWRS Hong, J.-D.; Jang, Changheui, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1973 - 1978, 2010-06-13 |
| Probabilistic Fracture Mechanics Application For Alloy 82/182 Welds In PWRs Hong, Jong-Dae; Jang, Changheui, Pressure Vessels & Piping (PVP) 2010, 2010-07-20 |
| Probabilistic Fracture Mechanics Application for PWSCC Risk Evaluation of Ni-base alloy welds in PWR Jang, Changheui; Jong-Dae Kim, ICG-EAC 2012, IGCEAC, 2012-05-14 |
| Probabilistic Safety Assessment for LILW Silo Repository in Earthquake Scenario Using Domestic Earthquake List 한솔찬; 조용흠; 윤종일, 2018 한국방사성폐기물학회 춘계학술발표회, Korean Radioactive Waste Society, 2018-06-01 |
| Probabilistic Safety Assessment on the Fault-Tolerant Mechanism of Digital I&C Systems Kang, Hyun Gook, 원자력학회 2000춘계학술발표회, 원자력학회, 2000 |
| Probabilistic Safety Criteria (PSC) Allocation for Optimum Design and Operation of a Nuclear Power Plant Cho, Nam-Zin; Jung, W.S, Proceedings of the First Korea/Japan Joint Workshop on Probabilistic Safety Assessment (PSA), 1992-11 |
| Probabilistic seismic risk assessment of caisson-type breakwaters Kim S.H.; Yi J.H.; Kim D.K., 15th International Offrshore and Polar Engineering Conference, ISOPE-2005, v.2005, pp.547 - 552, 2005-06-19 |
| Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock Jang, Changheui, SMiRT-18, 2005-08-10 |
| Procedures and Techniques for the PSA of Digital I＆C System 강현국; 엄흥섭; 장승철, 한국원자력학회 2006 추계학술발표회, 한국원자력학회, 2006-11-03 |
| Process Simulation of Off-Gas Treatment System in Korea Vitrification Facility Lee, Kun Jai, International Low-Level Waste Conference and Exhibit Show by EPRI, 1999 |
| Production of Multiply Charged Ions in Cylindrical Hall Thruster Plasmas Kim, Holak; Choe, Wonho; Lee, Seunghun; Doh, Keuntae; Lim, Youbong, 35th International Electric Propulsion Conference, Electric Rocket Propulsion Society (ERPS), 2017-10-10 |
| Progress in Modular Stellarator Fusion Power Research Reactor Conceptual Designs Lee, Kun Jai, 9th IAEA Int'l Conference on Plasma Physics and Controlled Nuclear Fusion REsearch, pp.387 - 398, 1983 |
| Progress in Multifunctional Metal Matrix Nanocomposites Ryu, Ho Jin, International Symposium on Innovation in Materials Processing, ISIMP 2021, Korean Powder Metallurgy Institute, 2021-10-26 |
| Progress in the Design of a Tritium Breeding Blankets for Testing in ITER Hong, BG; In, WK; Kim, Y; Lee, DW; Song, KW; Yoo, KH; Cho, S; et al, 21st IAEA Fusion Energy Conference, 2006-10 |
| Progress in the Pb-Bi cooled fast reactor PEACER development Kim C.H.; Hwang I.S.; Suh K.Y.; Shin J.G.; Yi K.W.; Lee, Kun Jai; Kim M.H.; et al, Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, pp.940 - 941, 2003-11-16 |
| Progress of accident analysis codes development for gas-cooled reactors Lee, W.-J.; Lim, H.-S.; Chang, J.-H.; No, Hee Cheon; Park, G.-C., International Meeting on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis, BE-2004, pp.137 - 144, 2004-11-14 |
| Properties of Tatanium-Nitride for High Level Waste Packaging Enhancement Candice Scheffing; Yim Man-Sung; Mohamed Bourham; Jag Kasichainula, Transactions of the American Nuclear Society, v.93, no.2005, pp.709 - 710, Transactions of the American Nuclear Society, 2005-11 |
| Properties of titanium-nitride for high level waste packaging enhancement Scheffing, Candice C.; Yim Man-Sung; Bourham, Mohamed A.; Kasichainula, Jagannadham, 2005 Winter Meeting - American Nuclear Society, v.93, no.2005, pp.709 - 710, Transactions of the American Nuclear Society, 2005-11 |
| Proportional-share scheduler for multimedia applications Kim Manhee; Lee Hyogun; Lee, Joonwon, Proceedings of the 1997 IEEE International Conference on Multimedia Computing and Systems, ICMCS, pp.484 - 491, 1997-06-03 |
| Proposal of Site Reuse and Waste Recycling in Kori-1 Nuclear Power Plant Decommissioning 이주호; 서영아; 임만성, 2015 Korean Radioactive Waste Society Conference Meeting, Korean Radioactive Waste Society, 2015-10-15 |
| Proposed Concept of a Passive Water Cooled Reactor without Emergency Core Cooling System Baek, WP; Lee, GJ; Lee, JY; Chang, Soon-Heung, '92 International Conference on Design and Safety of Advanced Nuclear Power Plant, pp.1 - 6, 1992-10 |
| Proposed Concept of a Water-Cooled Reactor with Passive Decay Heat Removal Capability Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting ot Review the Safety Features of New Reactor Design, 1991 |
| PROPOSING A WORKER’S MENTAL HEALTH ASSESSMENT USING BIO-SIGNALS SUH, Young A; Yim, Man-Sung, 3rd International Conference on Human Resource Development for Nuclear Power Programmes: Meeting Challenges to Ensure the Future Nuclear Workforce Capability, IAEA, 2018-05-31 |
| Prospect of CdZnTe Detector for Nuclear Medical Applications Cho, Gyuseong, 제2회 원자력 병원 핵의학 심포지움, 1998-04 |
| Prospects and Cost Estimation of Decommissioning in Korea Lee, Kun Jai, 1991 ASME Joint International Waste Management Conf., pp.609 - 613, 1991 |
| Proton Irradiation Effects on the Mechanical Properties of Zr-based metallic glasses Heo, Jaewon; Kim, S; Jo, Y; Ryu, S; Jang, Dongchan, Gordon Research Conferences on Structural Nanomaterials (GRC 2014), Gordon Research Conferences, 2014-07 |
Discover
Type
- 2,799 Article
- 5,616 Conference
- 430 Patent
- 918 Thesis(Master)
- 556 Thesis(Ph.D)
Open Access
- 152 OA Article
Date issued
- 1,250 2020 - 2024
- 4,359 2010 - 2019
- 2,657 2000 - 2009
- 1,431 1990 - 1999
- 449 1980 - 1989