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

Showing results 8761 to 8780 of 10265

8761
Thermal power estimation by fouling phenomena compensation using wavelet and principal component analysis

Heo, G; Choi, SS; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.31 - 40, 2000-06

8762
Thermal Power Estimation Using De-noising and an Autoassociative Neural Network in Nuclear Power Plant

Heo, GY; Choi, SS; Chang, Soon-Heung, '98 ANS Winter Meeting, ANS, 1998

8763
THERMAL POWER PREDICTION OF NUCLEAR-POWER-PLANT USING NEURAL NETWORK AND PARITY SPACE MODEL

ROH, MS; CHEON, SW; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.38, no.2, pp.866 - 872, 1991-04

8764
Thermal Property Simulation of ZrO2-based Nanocomposites for Inert Matrix Fuel

Vivek Raj; Mistarihi, Qusai; 류호진, 한국원자력학회 2015 춘계학술대회, 한국원자력학회, 2015-05-07

8765
Thermal-hydraulic analysis and design of printed circuit heat exchangers for KAIST Advanced Pyro-SFRs = KAIST Advanced Pyro-SFRs의 인쇄기판형 열교환기의 열수력적 분석 및 설계link

Kang, Gil-Beom; 강길범; et al, 한국과학기술원, 2013

8766
Thermal-hydraulic analysis of annular fuel-based assemblies of liquid metal reactors

Han, K.-H.; Chang, Soon-Heung, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.1, pp.38 - 46, American Nuclear Society, 2005-05-15

8767
Thermal-hydraulic analysis of mixed cores with optimized and standard fuel assemblies = 최적 핵연료 집합체와 표준 핵연료 집합체 장전 혼합 노심에 대한 열.수력 해석link

Kim, Se-Chang; 김세창; et al, 한국과학기술원, 1985

8768
Thermal-hydraulic analysis of the containment for design of passive containment cooling system = 피동 격납용기 냉각계통의 설계를 위한 격납용기의 열-유체 분석link

Park, Jong-Ha; 박종하; et al, 한국과학기술원, 1991

8769
Thermal-hydraulic Analysis of the GT-MHR Core using Axiomatic Design

Jeong, HD; Chang, Soon-Heung, NUTHOS-7, 2008-10-05

8770
Thermal-hydraulic characteristics evaluations of the printed circuit heat exchanger in a helium-water test loop

Kim, I.H.; No, Hee Cheon, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1749 - 1757, 2010-06-13

8771
Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop

No, Hee Cheon; Kim, In Hun, 한국원자력학회 추계발표회, 한국원자력학회, 2009

8772
Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop

No, Hee Cheon, the KNS Autumn Meeting

8773
Thermal-hydraulic design methodology and trade-off studies for a dual-salt breed-and-burn molten salt reactor

Kasam, Alisha; Lee, Jeong Ik; Shwageraus, Eugene, NUCLEAR ENGINEERING AND DESIGN, v.360, 2020-04

8774
Thermal-hydraulic evaluation of passive containment cooling system of improved APR plus during LOCAs

Jeon, Byong Guk; No, Hee-Cheon, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.190 - 198, 2014-10

8775
Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs

노희천; 전병국, KNS Spring, KNS Spring, 2014-05-29

8776
Thermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel = 사용후 핵연료의 중간건식저장에 대한 열유체 실험 및 해석link

Yoo, Seung-Hun; 류승훈; et al, 한국과학기술원, 2011

8777
Thermal-hydraulic experiments for the PCHE type steam generator

노희천; 신창욱, KNS Spring, KNS Spring, 2015-05-07

8778
Thermal-hydraulic performance of a printed circuit heat exchanger in an air test loop = 공기를 이용한 개방형계에서의 인쇄형 열교환기의 열수력학적 실험link

Song, Sung-Chu; 송성주; et al, 한국과학기술원, 2006

8779
Thermal-Hydraulic Performance Tests of PCHE Using Mixture-Gas for HTGRs

No Hee Cheon; Kim, In Hun, American Nuclear Society, 2011-06

8780
Thermal-hydraulic physical models for a Printed Circuit Heat Exchanger covering He, He-CO2 mixture, and water fluids using experimental data and CFD

Kim, In-Hun; No, Hee-Cheon, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.48, pp.213 - 221, 2013-07

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