Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference

Showing results 3901 to 3960 of 5616

3901
Preliminary Study on effects of ESS integrated nuclear power plants with increased penetration of renewable energy

조재완; 이정익, 한국원자력학회 2020춘계학술발표회, 한국원자력학회, 2020-05-21

3902
Preliminary Study on Optimization for S-CO2 Cycle coupled to ATOM Reactor

백정열; 이정익, 2018 한국원자력학회 추계학술발표회, 한국원자력학회, 2018-10-25

3903
Preliminary Study on Passive Cooling of Instrumentation and Control Room Using PCMs

조재완; 이정익, 한국원자력학회 2021 춘계학술발표회, 한국원자력학회, 2021-05-13

3904
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

3905
Preliminary Study on S-CO2 Leakage to High Pressure Water

이재준; 이정익, 2020 한국원자력학회 추계학술대회, 한국원자력학회, 2020-12-18

3906
Preliminary Study on Tank Design for S-CO2 Power Cycle Inventory Control

이재준; 오봉성; 백정열; 이정익, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-24

3907
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

3908
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

3909
Preliminary Test of Friction disk type turbine for S-CO2 cycle application

백승준; 김현태; 이정익, 2016 한국원자력학회 춘계학술발표회, 한국원자력학회, 2016-05-13

3910
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

3911
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

3912
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

3913
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

3914
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

3915
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

3916
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

3917
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

3918
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

3919
Present and Future of Safety Analysis Codes for High Temperature Gas-Cooled Reactors

No, Hee Cheon, NUTHOS-7 Keynote lecture

3920
Present Status of High Strength Low Ally Steels

김인섭, Steel Industry Seminar, The Korea Iron and Steel Association, 1981

3921
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

3922
Pressure Calculation of Intergranular Bubbles in UO2

김재준; 류호진, 2021 한국원자력학회 온라인 춘계학술발표회, 한국원자력학회, 2021-05-13

3923
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

3924
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

3925
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

3926
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

3927
Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant

Jang, Changheui, PVP 2000, 2000-07-24

3928
Principles of Small Angle Neutron Scattering

최성민, HANARO Cold Neutron School, HANARO Cold Neutron School, 2015-08

3929
Principles of Small Angle Neutron Scattering

최성민, 7th PLS-II Summer School, 포항가속기연구소, 2015-07-28

3930
Principles of Small Angle Neutron Scattering

최성민, The Cold Neutron Summer School 2012, 한국원자력연구원, 2012-07

3931
Principles of Small Angle X-ray Scattering

최성민, The 4th PLS-II Summer School and Tutorials, 포항가속기연구소, 2012-07

3932
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

3933
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

3934
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

3935
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

3936
Probabilistic Fracture Mechanics Application For Alloy 82/182 Welds In PWRs

Hong, Jong-Dae; Jang, Changheui, Pressure Vessels & Piping (PVP) 2010, 2010-07-20

3937
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

3938
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

3939
Probabilistic Safety Assessment on the Fault-Tolerant Mechanism of Digital I&C Systems

Kang, Hyun Gook, 원자력학회 2000춘계학술발표회, 원자력학회, 2000

3940
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

3941
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

3942
Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

Jang, Changheui, SMiRT-18, 2005-08-10

3943
Procedures and Techniques for the PSA of Digital I&C System

강현국; 엄흥섭; 장승철, 한국원자력학회 2006 추계학술발표회, 한국원자력학회, 2006-11-03

3944
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

3945
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

3946
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

3947
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

3948
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

3949
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

3950
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

3951
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

3952
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

3953
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

3954
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

3955
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

3956
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

3957
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

3958
Prospect of CdZnTe Detector for Nuclear Medical Applications

Cho, Gyuseong, 제2회 원자력 병원 핵의학 심포지움, 1998-04

3959
Prospects and Cost Estimation of Decommissioning in Korea

Lee, Kun Jai, 1991 ASME Joint International Waste Management Conf., pp.609 - 613, 1991

3960
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

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