NE-Journal Papers(저널논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 2701 to 2720 of 2796

2701
Characterization of aquatic groundwater colloids by a laser-induced breakdown detection and ICP-MS combined with an asymmetric flow field-flow fractionation

Baik, Min-Hoon; Yun, Jong-Il; Bouby, Muriel; Hahn, Pil-Soo; Kim, Jae-Il, KOREAN JOURNAL OF CHEMICAL ENGINEERING, v.24, no.5, pp.723 - 729, 2007-09

2702
Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11

2703
Optimization of the hybrid sulfur cycle for nuclear hydrogen generation

Jeong, Yong Hoon; Kazimi, Mujid S, NUCLEAR TECHNOLOGY, v.159, no.2, pp.147 - 157, 2007-08

2704
Formation of aquatic Th(IV) colloids and stabilization by interaction with Cm(III)/Eu(III)

Yun, Jong-Il; Kim, MA; Panak, PJ; Kim, JI; Fanghanel, T, JOURNAL OF PHYSICAL CHEMISTRY B, v.110, no.11, pp.5416 - 5422, 2006-03

2705
Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363, 2004-09

2706
An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube

Lee, YH; Kim, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.229, no.1, pp.47 - 58, 2004-04

2707
Advisory system for the diagnosis of lost electric output in nuclear power plants

Heo, G; Chang, Soon-Heung; Choi, SS; Choi, GH; Jee, MH, EXPERT SYSTEMS WITH APPLICATIONS, v.29, no.4, pp.747 - 756, 2005-11

2708
CHF characteristics of R-134a flowing upward in uniformly heated vertical tube

Kim, CH; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.11, pp.2242 - 2249, 2005-05

2709
Algebraic approach for the diagnosis of turbine cycles in nuclear power plants

Heo, G; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.235, no.14, pp.1457 - 1467, 2005-06

2710
Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a pool

Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.12, pp.2407 - 2419, 2005-06

2711
Experimental study on the effect of angles and positions of mixing vanes on CHF in a 2x2 rod bundle with working fluid R-134a

Shin, BS; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.235, no.16, pp.1749 - 1759, 2005-07

2712
Visualization of a principle mechanism of critical heat flux in pool boiling

Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12

2713
Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes

Kim, CH; Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.14, pp.2868 - 2877, 2005-07

2714
INCIPIENT MULTIPLE-FAULT DIAGNOSIS IN REAL-TIME WITH APPLICATION TO LARGE-SCALE SYSTEMS

CHUNG, HY; Bien, Zeung nam; PARK, JH; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.41, no.4, pp.1703 - 2, 1994-08

2715
OPTIMAL TESTING INPUT SETS FOR REDUCED DIAGNOSIS TIME OF NUCLEAR-POWER-PLANT DIGITAL ELECTRONIC-CIRCUITS

KIM, DS; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.41, no.1, pp.316 - 2, 1994-02

2716
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes

Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02

2717
The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids

Lee, Kwi Lim; Bang, In Cheol; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.1-2, pp.91 - 103, 2008-01

2718
Effects of mechanical vibration on critical heat flux in vertical annulus tube

Kim, Dae Hun; Lee, Yong Ho; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.237, no.9, pp.982 - 987, 2007-05

2719
Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01

2720
Flow analysis using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling

Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.33, no.11-12, pp.966 - 974, 2006-07

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