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

Showing results 4381 to 4400 of 10268

4381
Experimental and CFD studies of condensation with non-condensable and air natural convection in a passive decay heat removal system = 비응축 가스를 포함한 응축과 공기자연대류를 이용한 피동 잔열 제거 계통에 관한 실험 및 CFD 연구link

Kim, Do Yun; No, Hee Cheon; et al, 한국과학기술원, 2019

4382
Experimental and computational analysis of gas natural circulation loop

Lee, JeongIk; Hejzlar,P, International Congress on Advances in Nuclear Power Plants (ICAPP 2007), French Nuclear Energy Society, 2007-05-14

4383
Experimental and Numerical Analysis of S-CO2 Critical Flow for SFR Recovery System Design

Kim, Mim Seok; Jung, Hwa Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05

4384
Experimental and numerical evaluation of the neutral beam deposition profile in KSTAR

Na, B; Kang, J; Lee, MW; Jung, L; Hahn, SH; Yoo, JW; Jeong, JH; et al, FUSION ENGINEERING AND DESIGN, v.185, 2022-12

4385
Experimental and numerical investigation of supercritical CO2 test loop transient behavior near the critical point operation

Bae, Seong Jun; Ahn, Yoonhan; Lee, Jekyoung; Kim, Seong Gu; Baik, Seungjoon; Lee, Jeong-Ik, APPLIED THERMAL ENGINEERING, v.99, pp.572 - 582, 2016-04

4386
Experimental and numerical investigations of thermal-hydraulic characteristics for the design of a Printed Circuit Heat Exchanger (PCHE) in HTGRs = 고온가스냉각로의 PCHE 설계를 위한 열수력 특성의 실험 및 수치적 연구link

Kim, In-Hun; 김인훈; et al, 한국과학기술원, 2012

4387
Experimental and Numerical Investigations on S-CO2 Critical Flow with Implications in Turbomachinery Seal Design

Kim, Min Seok; Jung, Hwa-Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong-Ik, The 9th National Congress of Fluids Engineering, 한국가시화정보학회, 2016-08-10

4388
Experimental and Numerical Studies of Supercritical CO2 Test Loop with GAMMA code

Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Lee, Jeong-Ik, NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety(2016), American Nuclear Society, 2016-10-09

4389
EXPERIMENTAL AND NUMERICAL STUDY OF CRITICAL FLOW MODEL DEVELOPMENT FOR SUPERCRITICAL CO2 POWER CYCLE APPLICATION

KIM, MINSEOK; Oh, Bong-seong; Jung, Hwa-Young; Bae, Seong Jun; Lee, Jeong-Ik, ASME Turbo Expo 2018: Turbomachinery Technical Conference and Exposition, ASME, 2018-06-13

4390
Experimental and Numerical Study of Supercritical CO₂ Test Loop Transient Conditions

Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Baik, Seungjoon; Lee, Jekyoung; Lee, Jeong-Ik, The First Pacific Rim Thermal Engineering Conference(2016), American Society of Thermal and Fluids Engineers, 2016-03-13

4391
Experimental and numerical study on the chf performance of mixing vane = 혼합날개의 임계열유속 성능에 관한 실험적 연구와 수치해석link

Shin, Byung-Soo; 신병수; et al, 한국과학기술원, 2008

4392
Experimental and numerical study on the natural circulation phenomena in the pool-type LMFBR = 풀형 고속 증식로에서의 자연 순환 현상에 관한 실험 및 수치 해석적 연구link

Lee, Yong-Bum; 이용범; Cho, Mann; Chang, Soon-Heung; et al, 한국과학기술원, 1985

4393
Experimental and theoretical investigation of reflux condensation phenomena in a vertical U-tube = 수직관내에서의 역류 응축 현상에 대한 실험 및 이론적 연구link

Jun, Hyung-Gil; 전형길; et al, 한국과학기술원, 1990

4394
Experimental and theoretical investigation of waterhammer induced by steam-water countercurrent flow a long horizontal pipe = 긴 수평관에서 기액 역층류 유동에 의한 수격작용에 관한 실험 및 이론적 연구link

Nam, Ho-Yun; 남호윤; et al, 한국과학기술원, 1994

4395
Experimental and theoretical studies on the high pressure vessel = 원자로 가압용기로부터 고압용융물 방출에 관한 실험 및 이론적 연구link

So, Dong-Sup; 소동섭; et al, 한국과학기술원, 1992

4396
Experimental Approach to Effect Estimation of Decision Support Systems

이승준; 성풍현, 한국원자력학회 2007 춘계학술발표대회, 한국원자력학회, 2007-05-10

4397
Experimental Approaches on Flow Accelerated Corrosion Behavior of CANDU Feeder Piping

Kim, In Sup, The 4th International Workshop on the Integrity of Nuclear Components, 2002

4398
Experimental Assessment of Critical Heat Flux for the Real Condition of IVR-ERVC Strategy

Park, Hae Min; Jung, Jun Yeong; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-12

4399
Experimental benchmarks and simulation of GAMMA-T for overcooling and undercooling transients in HTGRs coupled with MED desalination plants

Kim, Ho-Sik; Kim, In-Hun; No, Hee-Cheon; Jin, Hyung-Gon, NUCLEAR ENGINEERING AND DESIGN, v.259, pp.29 - 40, 2013-06

4400
Experimental CHF study for the top of the reactor vessel lower head = 원자로용기 하부헤드 상부에서의 임계열유속에 관한 실험적 연구link

Park, Hae-Min; 박해민; et al, 한국과학기술원, 2014

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