Browse "NE-Journal Papers(저널논문)" byTitle

Showing results 141 to 160 of 2594

141
A PC-BASED WATER-LEVEL CONTROLLER FOR NUCLEAR STEAM-GENERATORS

NA, MG; KIM, SP; CHUNG, WK; LEE, KJ; SONG, JS; No, Hee Cheonresearcher; LEE, JY, ANNALS OF NUCLEAR ENERGY, v.21, no.10, pp.589 - 600, 1994-10

142
A personal thermoluminescence dosimeter using LiF : Mg,Cu,Na,Si detectors for photon fields

Jung, HY; Lee, Kun Jairesearcher; Kim, JL, APPLIED RADIATION AND ISOTOPES, v.59, no.1, pp.87 - 93, 2003-07

143
A photographic study on the near-wall bubble behavior in subcooled flow boiling

Chang, Soon-Heungresearcher; Bang, IC; Baek, WP, INTERNATIONAL JOURNAL OF THERMAL SCIENCES, v.41, no.7, pp.609 - 618, 2002-07

144
A Pilot Study of Chronological Microbiota Changes in a Rat Apical Periodontitis Model

Park, Ok-Jin; Jeong, Moon-Hee; Lee, Eun-Hye; Cho, Mi-Ran; Hwang, Jaehong; Cho, Seungryongresearcher; Yun, Cheol-Heui; et al, MICROORGANISMS, v.8, no.8, 2020-08

145
A point model for the design of a sulfur trioxide decomposer for the SI cycle and comparison with a CFD model

Lee, You Ho; Lee, JeongIkresearcher; No, Hee Cheonresearcher, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.35, no.11, pp.5210 - 5219, 2010-06

146
A practical method for accurate quantification of large fault trees

Choi, Jong Soo; Cho, Nam-Zinresearcher, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.92, no.7, pp.971 - 982, 2007-07

147
A probabilistic approach for determining the control mode in CREAM

Kim, MC; Seong, Poong-Hyunresearcher; Hollnagel, E, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.2, pp.191 - 199, 2006-02

148
A PROBABILISTIC SAFETY CRITERION FOR CORE MELT FREQUENCY BASED ON THE DISTRIBUTION OF THE PUBLICS SAFETY GOALS

RA, KY; Lee, Byong-Whi; Chang, Soon-Heungresearcher, NUCLEAR TECHNOLOGY, v.101, no.2, pp.149 - 158, 1993-02

149
A PROBABILISTIC STUDY OF LIMITING CONDITIONS OF OPERATION FOR THE REACTOR PROTECTION SYSTEM

PAPAZOGLOU, IA; Cho, Nam-Zinresearcher, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.45, pp.376 - 377, 1983

150
A Procedure for Statistical Thermal Margin Analysis Using Response Surface Method and Monte Carlo Technique

김현군; 이영환; 김태운; 장순흥researcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.18, no.1, pp.38 - 47, 1986

151
A procedure to predict subcooled-water-flow-boiling CHF in uniformly heated tubes for high-heat-flux applications

Kwon, YM; Chang, Soon-Heungresearcher, NUCLEAR TECHNOLOGY, v.130, no.3, pp.310 - 328, 2000-06

152
A PSA-based vital area identification methodology development

Park, CK; Jung, WS; Yang, JE; Kang, Hyun Gookresearcher; Gurpinar, A; Kim, SC, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.82, no.2, pp.133 - 140, 2003-11

153
A pseudo-discrete algebraic reconstruction technique (PDART) prior image-based suppression of high density artifacts in computed tomography

Pua, Rizza; Park, Miran; Wi, Sunhee; Cho, Seungryongresearcher, NUCLEAR INSTRUMENTS METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, v.840, pp.42 - 50, 2016-12

154
A quality control method for nuclear instrumentation and control systems based on software safety prediction

Son, HS; Seong, Poong-Hyunresearcher, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.47, no.2, pp.421 - 2, 2000-04

155
A quantification method for fault coverage of NPP digital systems combining mathematical analysis and computer simulation

Kim, M.C.; Kim, S.J.; Seong, Poong-Hyunresearcher, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.88, pp.29</div> - 29</div>, 2003

156
A quantitative approach to modeling the information flow of diagnosis tasks in nuclear power plants

Kim, JH; Seong, Poong-Hyunresearcher, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.80, no.1, pp.81 - 94, 2003-04

157
A Quantitative Approach to Modeling the Information Processing of NPP Operators

Kim , Jong Hyun; Seong, Poong-Hyunresearcher, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.86, no.1, pp.18 - 19, 2002-06

158
A quantitative assessment method for safety-critical signal generation failures in nuclear power plants considering dynamic dependencies

Shin, Seung-Ki; Seong, Poong-Hyunresearcher, ANNALS OF NUCLEAR ENERGY, v.38, no.2-3, pp.269 - 278, 2011-02

159
A Quantitative Evaluation of Chemical and Volume control System Design Simplification

Son, Han Seong; Seong, Poong Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.27, no.5, pp.753 - 759, 1995-10

160
A quantitative impact analysis of sensor failures on nuclear power plant operators in accident situations

Kim, M.C.; Seong, Poong-Hyunresearcher, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.92, no.1, pp.451</div> - 451</div>, 2005

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