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

Showing results 6301 to 6320 of 9051

6301
Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application

남승현; 이정익researcher; 장순흥researcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-30

6302
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

6303
Preliminary Validation and Verification of TURBO_DESIGN for S-CO2 Axial Compressor

Lee, Jekyoung; Lee, JeongIkresearcher; Ahn, Yoonhan; Kim, Seong Gu; Yoon, Ho Joon; Yacine Addad, Transactions of the Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2012-05

6304
Premature and Stable Critical Heat Flux for Downward Flow in a Narrow Rectangular Channel

Lee, Juhyung; Jo, Dae Seong; Chang, Soon Heungresearcher; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

6305
Preparation and characterization of magnetic nanoparticles and their silica egg-yolk-like nanostructures: A prospective multifunctional nanostructure platform

Chen, Minghai; Kim, Yong-Nam; Li, Cuncheng; Cho, Sung-Ohresearcher, JOURNAL OF PHYSICAL CHEMISTRY C, v.112, no.17, pp.6710 - 6716, 2008-05

6306
Preparation of Cesium (Cs) Release Test for Verifying Diffusion Coefficient in the IG-110 Graphite Matrix

Baek, Je Kyun; Ryu, Ho Jinresearcher; Yeo, Sung Hwan; Lee, Young Woo; Lee, Jeong Mook, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27

6307
Preparedness of Operation Teams' non-technical Skills in a Main Control Room of Nuclear Power Plants to Manage Emergency Situations

임호빈; 김아름; 성풍현researcher, 한국원자력학회 2012 춘계학술발표대회, 한국원자력학회, 2012-05-18

6308
Present and Future of Safety Analysis Codes for High Temperature Gas-Cooled Reactors

No, Hee Cheonresearcher, NUTHOS-7 Keynote lecture

6309
Present Status of High Strength Low Ally Steels

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

6310
Pressure and Magnetic Field Effects on CHF of Magnetic Nanofluids

Lee, Taeseung; Jeong, Yong Hoonresearcher, 2012 ANS Winter Meeting and Nuclear Technology Expo Embedded Topical Meeting, American Nuclear Society, 2012-11

6311
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 Hoonresearcher, The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Thermal Hydraulics Divisions of AESJ, KNS, 2012-12

6312
Pressure Effect on Pool Boiling Critical Heat Flux in Water-based Nanofluids with Alumina and Magnetite Nanoparticles

Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-15), N.IN.E, 2013-05-13

6313
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

6314
PRESSURE-DROP AND INTERFACE DRAG COEFFICIENT IN 2-PHASE FLOW OF SODIUM

No, Hee Cheonresearcher; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.82, no.3, pp.235 - 242, 1982

6315
Pressurized Environments and Effect of Silica Gel Amount on Depressurization Inside the Containment

KAM, DONG HOON; Jeong, Yong Hoonresearcher, The 18th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-18), American Nuclear Society, 2019-08-20

6316
Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

Jhung, MJ; Park, YW; Jang, Changheuiresearcher, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.76, no.12, pp.813 - 823, 1999-10

6317
Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant

Jang, Changheuiresearcher, PVP 2000, 2000-07-24

6318
PRESSURIZED WATER-REACTOR CORE PARAMETER PREDICTION USING AN ARTIFICIAL NEURAL NETWORK

KIM, HG; Chang, Soon-Heungresearcher; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.113, no.1, pp.70 - 76, 1993-01

6319
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

6320
Principles of Small Angle Neutron Scattering

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

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