Browse "NE-Journal Papers(저널논문)" by Title 

Showing results 2581 to 2600 of 2793

2581
Thermal energy storage unit (TESU) design for high round-trip efficiency of liquid air energy storage (LAES)

Kim, Kyoung Joong; Kim, Bokeum; Byeon, Byeongchang; Jeong, Sangkwon; Lee, Jeong-Ik; Park, Junghwan; Jamal, Aqil, CRYOGENICS, v.128, 2022-12

2582
Thermal Enhancement of Absorption of EM Radiation in a Hot Magnetoplasma Slab

Bawa'aneh, Muhammad S.; Al-Khateeb, A. M.; Ghim, Young-chul, IEEE TRANSACTIONS ON ANTENNAS AND PROPAGATION, v.66, no.12, pp.6525 - 6530, 2018-12

2583
Thermal expansion of UO2 and simulated DUPIC fuel

Kang, KH; Ryu, Ho Jin; Song, KC; Yang, MS, JOURNAL OF NUCLEAR MATERIALS, v.301, no.2-3, pp.242 - 244, 2002-03

2584
Thermal feedback transient analysis of a pebble fuel based on the two-temperature homogenized model

Cho, Nam-Zin; Yu, H.; Kim, J.W., TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.99, no.0, pp.677 - 679, 2008

2585
Thermal Fluctuation and Elasticity of Lipid Vesicles Interacting with Pore-Forming Peptides

Lee, Ji-Hwan; Choi, SungMin; Doe, Changwoo; Faraone, Antonio; Pincus, Philip A.; Kline, Steven R., PHYSICAL REVIEW LETTERS, v.105, no.3, 2010-07

2586
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

2587
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

2588
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

2589
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

2590
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

2591
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

2592
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

2593
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

2594
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

2595
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

2596
Thermal-hydraulic study of air-cooled passive decay heat removal system for APR plus under extended station blackout

Kim, Do Yun; No, Hee Cheon; Yoon, Ho Joon; Lim, Sang Gyu, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.60 - 72, 2019-02

2597
Thermally reversible pluronic/heparin nanocapsules exhibiting 1000-fold volume transition

Choi, SH; Lee, JH; Choi, SungMin; Park, TG, LANGMUIR, v.22, no.4, pp.1758 - 1762, 2006-02

2598
Thermally Switchable One- and Two-Dimensional Arrays of Single-Walled Carbon Nanotubes in a Polymeric System

Do, Chang-Woo; Jang, Hyung-Sik; Kim, Tae-Hwan; Kline, Steven R.; Choi, Sung-Min, JOURNAL OF THE AMERICAN CHEMICAL SOCIETY, v.131, no.45, pp.16568 - 16572, 2009-11

2599
Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor

Tak, Nam-Il; Kim, Yonghee; Choi, Jae-Hyuk; Lee, Won Jae, NUCLEAR ENGINEERING AND DESIGN, v.238, no.10, pp.2821 - 2827, 2008-10

2600
Thermodynamic analysis of compressed and liquid carbon dioxide energy storage system integrated with steam cycle for flexible operation of thermal power plant

Chae, YongJae; Lee, Jeong-Ik, ENERGY CONVERSION AND MANAGEMENT, v.256, 2022-03

Discover

Type

Open Access

Date issued

Subject

. next

rss_1.0 rss_2.0 atom_1.0