NE-Journal Papers(저널논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 1581 to 1600 of 2796

1581
An Abstraction Hierarchy based mobile PC display design in NPP maintenance considering the level of expertise

Bin Yim, Ho; Kim, In; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.241, no.5, pp.1881 - 1888, 2011-05

1582
AN IMPROVED MONTE CARLO METHOD APPLIED TO THE HEAT CONDUCTION ANALYSIS OF A PEBBLE WITH DISPERSED FUEL PARTICLES

Song, Jae Hoon; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.3, pp.279 - 286, 2009-04

1583
Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor

Yun, Sung-Hwan; Cho, Nam-Zin; Ahn, Mu-Young; Cho, Seung-Yon, FUSION ENGINEERING AND DESIGN, v.85, no.10-12, pp.2222 - 2226, 2010-12

1584
MONTE CARLO DEPLETION UNDER LEAKAGE-CORRECTED CRITICAL SPECTRUM VIA ALBEDO SEARCH

Yun, Sung-Hwan; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.42, no.3, pp.271 - 278, 2010-06

1585
Daubechies Wavelet Method for Angular Solution of the Neutron Transport Equation

Zheng, Youqi; Wu, Hongchun; Cao, Liangzhi; Cho, Nam-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.164, no.2, pp.87 - 104, 2010-02

1586
FBDVerifier: Interactive and Visual Analysis of Counter-example in Formal Verification of Function Block Diagram

Jee, Eunk Young; Jeon, Seungjae; Cha, Sungdeok; Koh, Kwangyong; Yoo, Junbeom; Park, Geeyong; Seong, Poong-Hyun, JOURNAL OF RESEARCH AND PRACTICE IN INFORMATION TECHNOLOGY, v.42, no.3, pp.171 - 188, 2010-08

1587
Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Jhung, Myung Jo; Choi, Young Hwan; Jang, Changheui, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.46, no.3, pp.310 - 315, 2009-03

1588
Quantification of unavailability caused by random failures and maintenance human errors in nuclear power plants

Khalaquzzman, Mohammad; Kang, Hyun-Gook; Kim, Man-Cheol; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.240, no.6, pp.1606 - 1613, 2010-06

1589
A steam generator model identification and robust H-infinity controller design with nu-gap metric for a feedwater control system

Sohn, Jong Joo; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.37, no.2, pp.180 - 195, 2010-02

1590
Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal Shock

Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Chang, Yoon Suk; Xu, Xiangyuan; Kim, Jong Min; Kim, Jong Wook; et al, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.12, pp.1131 - 1139, 2010-12

1591
A computational model for evaluating the effects of attention, memory, and mental models on situation assessment of nuclear power plant operators

Lee, Hyun-Chul; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.94, no.11, pp.1796 - 1805, 2009-11

1592
A REVIEW OF STUDIES ON OPERATORS INFORMATION SEARCHING BEHAVIOR FOR HUMAN FACTORS STUDIES IN NPP MCRS

Ha, Jun Su; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.3, pp.247 - 270, 2009-04

1593
Attentional-Resource Effectiveness Measures in Monitoring and Detection Tasks in Nuclear Power Plants

Ha, Jun Su; Seong, Poong-Hyun, IEEE TRANSACTIONS ON SYSTEMS MAN AND CYBERNETICS PART A-SYSTEMS AND HUMANS, v.40, no.5, pp.993 - 1008, 2010-09

1594
Reliability graph with general gates (RGGG): A novel method for reliability analysis

Seong, Poong-Hyun; SHIN, Seung-Ki, INTERNATIONAL ELECTRONIC JOURNAL OF NUCLEAR SAFETY AND SIMULATION, v.1, no.3, pp.180 - 197, 2010-10

1595
Development of an evaluation method for the quality of NPP MCR operators communication using Work Domain Analysis (WDA)

Jang, Inseok; Park, Jinkyun; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.38, no.6, pp.1264 - 1273, 2011-06

1596
Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method

Yun, Sung-Hwan; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.37, no.12, pp.1649 - 1658, 2010-12

1597
Design of an Integrated Operator Support System for Advanced NPP MCRs: Issues and Perspectives

LEE, Seung Jun; Seong, Poong-Hyun, NUCLEAR SAFETY AND SIMULATION, v.1, no.4, pp.348 - 368, 2010-12

1598
DIAMETRAL CREEP PREDICTION OF THE PRESSURE TUBES IN CANDU REACTORS USING A BUNDLE POSITION-WISE LINEAR MODEL

Lee, Sung-Han; Kim, Dong-Su; Lee, Sim-Won; No, Young-Gyu; Na, Man-Gyun; Lee, Jae-Yong; Kim, Dong-Hoon; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.43, no.3, pp.301 - 308, 2011-06

1599
Situation assessment model for nuclear power plant operators and its application

Lee, H.-C.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.102, no.0, pp.165 - 166, 2010

1600
Overview of KSTAR initial operation

Kwon, M.; Oh, Y. K.; Yang, H. L.; Na, H. K.; Kim, Y. S.; Kwak, J. G.; Kim, W. C.; et al, NUCLEAR FUSION, v.51, no.9, 2011-09

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