Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 7281 to 7300 of 10372
| 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 effects on critical heat flux under low pressure and low flow conditions = 저압 저유속 조건에서의 임계 열유속에 대한 압력 영향 연구link Kim, Hong-Chae; 김홍채; et al, 한국과학기술원, 1997 |
| 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 |
| PRESSURE-DROP AND INTERFACE DRAG COEFFICIENT IN 2-PHASE FLOW OF SODIUM No, Hee Cheon; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.82, no.3, pp.235 - 242, 1982 |
| 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 analyses of a reactor pressure vessel using critical crack depth diagrams Jhung, MJ; Park, YW; Jang, Changheui, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.76, no.12, pp.813 - 823, 1999-10 |
| Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant Jang, Changheui, PVP 2000, 2000-07-24 |
| PRESSURIZED WATER-REACTOR CORE PARAMETER PREDICTION USING AN ARTIFICIAL NEURAL NETWORK KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.113, no.1, pp.70 - 76, 1993-01 |
| Pressurizer surge line thermal-hydraulic analysis algorithm development = 가압기 연결관의 열수력적 해석 방법 개발link Kim, Hee-Cheol; 김희철; Chang, Soon-Heung; Han, Ki-In; et al, 한국과학기술원, 1990 |
| 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 |
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