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

Showing results 8801 to 8820 of 10333

8801
Thermal Hydraulic Analysis of Thorium Fuel Assemblies Loaded with Annular Seed Pins

Han, KH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2002

8802
Thermal hydraulic analysis of thorium fuel assemblies loaded with annular seed pins = 환형 시드 연료봉이 장착된 토륨 핵연료 집합체의 열수력 분석에 관한 연구link

Han, Kyu-Hyun; 한규현; et al, 한국과학기술원, 2002

8803
Thermal Hydraulic Analysis of Thorium-based Annular Fuel Assemblies

Han, KH; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10

8804
Thermal hydraulic behavior analysis of VANAM-M3(ISP-37) experiment using CINEMA code

김요한; 정운호; 박순호; 정용훈, 2022 한국원자력학회 춘계학술발표회, 한국원자력학회, 2022-05-19

8805
Thermal hydraulic behavior in the deteriorated turbulent heat transfer regime for a gas-cooled reactor

Kim, Hyeonil; Lee, JeongIk; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.240, no.4, pp.783 - 795, 2010-04

8806
Thermal hydraulic challenges of Gas Cooled Fast Reactors with passive safety features

Pope, Michael A.; Lee, JeongIk; Hejzlar, Pavel; Driscoll, Michael J., NUCLEAR ENGINEERING AND DESIGN, v.239, no.5, pp.840 - 854, 2009-05

8807
Thermal Hydraulic Design Parameters Study for Severe Accidents Using Neural Network

Roh, CH; Chang, KS; Chang, Soon-Heung, The 6th International Conference on Nuclear Engineering, 1998

8808
Thermal hydraulic performance analysis of a printed circuit heat exchanger using a helium-water test loop and numerical simulations

Kim, In-Hun; No, Hee-Cheon, APPLIED THERMAL ENGINEERING, v.31, no.17-18, pp.4064 - 4073, 2011-12

8809
Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations

Kim, In-Hun; No, Hee-Cheon; Lee, Jeong-Ik; Jeon, Yong-Guk, NUCLEAR ENGINEERING AND DESIGN, v.239, no.11, pp.2399 - 2408, 2009-11

8810
Thermal Hydraulic Performance of the Printed Circuit Heat Exchanger in a Helium Test Loop

No, Hee Cheon, Nthas6 2008

8811
Thermal hydraulic performance of the printed circuit heat exchanger in air and helium test loops = 공기와 헬륨 실험루프를 이용한 인쇄형 열교환기의 열유체성능 연구link

Kim, In-Hun; 김인훈; et al, 한국과학기술원, 2008

8812
Thermal hydraulic-Mechanic Integrated Simulation for Advanced Cladding Thermal Shock Fracture Analysis during Reflood Phase in LBLOCA

Son, Seongmin; Lee, Youho; Cho, Jaewan; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12

8813
Thermal loading perspective on U.S. nuclear waste repository needs

Stahala, Mike P.; Yim Man-Sung; McNelis, David N., 2006 Annual Meeting - American Nuclear Society, v.94, no.2006, pp.329 - 330, Transactions of the American Nuclear Society, 2006-06

8814
Thermal Loading Perspective on U.S. Nuclear Waste Repository Needs

Mike Stahala; Yim Man-Sung; David McNelis, Transactions of the American Nuclear Society, v.94, no.2006, pp.329 - 330, American Nuclear Society, 2006-06

8815
Thermal Performance Evaluation of Spent Fuel Pool Cooling System with Water Jacket and Heat Pipe

이상훈; 이민석; 박우성; 정용훈, 2023 한국원자력학회 춘계학술발표회, 한국원자력학회, 2023-05-18

8816
THERMAL PERFORMANCE OF MULTILAYER PVD TUNGSTEN COATING FOR THE FIRST WALL APPLICATION IN NUCLEAR FUSION DEVICES

Kim, Hyunmyung; Lee, Ho Jung; Jang, Changheui, FUSION SCIENCE AND TECHNOLOGY, v.68, no.2, pp.378 - 382, 2015-09

8817
Thermal performance of multilayer PVD tungsten coating for the ITER first wall panels application = ITER 플라즈마 대면재 적용을 위한 다층구조 텅스텐코팅 열 성능평가link

Kim, Hyunmyung; 김현명; et al, 한국과학기술원, 2015

8818
Thermal Performance Test through On-line Turbine Cycle Performance Monitoring in Nuclear Power Plants

Heo, GY; Lee, SJ; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999

8819
Thermal power estimation based on a neural network and principal component analysis in nuclear power plants = 신경회로망과 주성분 분석법을 이용한 원자력발전소 열출력 예측link

Heo, Gyun-Young; 허균영; et al, 한국과학기술원, 1999

8820
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

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