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

Showing results 121 to 140 of 8997

121
A core design concept for multi-purpose research reactors

Seo, Chul-Gyo; Cho, Nam-Zinresearcher, NUCLEAR ENGINEERING AND DESIGN, v.252, pp.34 - 41, 2012-11

122
A core design concept for multi-purpose research reactors = 다목적 연구로를 위한 노심 설계 개념link

Seo, Chul-Gyo; 서철교; et al, 한국과학기술원, 2013

123
A correction method for heated length effect in critical heat flux prediction

Lee, YH; Baek, WP; Chang, Soon-Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.1 - 11, 2000-06

124
A Correlation for Critical Pressure with Subcooled Upstream Conditions

전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.357 - 370, 1990

125
A Criterion for the Onset of Slugging in Horizontal Stratified Air-Water Countercurrent Flow

Chun, Moon Hyun, Proc. of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics. (NURETH-7), pp.93 - 110, 1995

126
A CRITICAL HEAT-FLUX MODEL BASED ON MASS, ENERGY, AND MOMENTUM BALANCE FOR UPFLOW BOILING AT LOW QUALITIES

Chang, Soon-Heungresearcher; LEE, KW, NUCLEAR ENGINEERING AND DESIGN, v.113, no.1, pp.35 - 50, 1989-04

127
A Critical Review of the Current PWR Containment Response Analysis Methodologies for Postulated Severe Accident

Chun, Moon Hyun, Proc. of Third Int'l. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins. (NUPTHO-3), 1988

128
A CRUD deposit model on boiling surfaces for AOA assessment = AOA 예측을 위한 비등 면에서의 CRUD 침적 모델 개발link

Kim, Min Ju; 김민주; et al, 한국과학기술원, 2015

129
A Decision-Theoretic Methodology for Reliability and Risk Allocation in Nuclear Power Plant

Cho, Nam-Zinresearcher; Papazoglou, I.A; Bari, R.A; El-Bassioni, A, Proc. of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, v.1, pp.1 - 10, 1985-02

130
A Dependability Estimation of Microprocessor-Base Software Under Memory Faults Using Stochastic Activity Network(SAN)

Choi, Jong Gyun; Seong, Poong-Hyunresearcher, Proc. of the Korean Nuclear Society, 1996-05

131
A Dependability Modeling of Software under Memory Faults for Digital System in Nuclear Power Plants

Park, Jong-Gyun; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.29, no.6, pp.433 - 443, 1997-12

132
A design and physics study of a compact sodium-cooled breed-and-burn fast reactor = 소형 소듐냉각 진행파원자로 개념연구 및 노물리 특성고찰link

Hartanto, Donny; Donny Hartanto; et al, 한국과학기술원, 2015

133
A Design Guide of Digital I&C Systems from the Viewpoint of PSA

Kang, Hyun Gookresearcher, Core University Program, 2001

134
A design of a valid signal selecting and position decoding ASIC for PET using silicon photomultipliers

Cho, Minsik; Lim, Kyung Taek; Kim, H; Yeom, JY; Kim, J; Lee, Chae-Hun; Choi, H; et al, JOURNAL OF INSTRUMENTATION, v.12, 2017-01

135
A design of a valid signal selecting and position decoding ASIC for PET using silicon photomultipliers

Cho, Minsik; Lim, Kyung Taek; Kim, H; Yeom, JY; Kim, J; Lee, Chae-Hun; Choi, H; et al, JOURNAL OF INSTRUMENTATION, v.12, 2017-01

136
A design of the high frame-rate and wide-input range ADC using complementary dual-slope for industrial NDT = 비파괴 검사에 쓰이는 빠른 프레임과 넓은 입력 범위를 가지는 상보적 램프 신호로 구현된 ADClink

Lee, Dae-Hee; 이대희; et al, 한국과학기술원, 2012

137
A design study of near-isothermal centrifugal compressor in a supercritical CO2 cycle for SMR application

Jeong, Yongju; Lee, Jeong-Ikresearcher; Heo, Jin Young; Cho, Seong Kuk, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety, Chinese Nuclear Society, 2018-10-14

138
A Determination of Bias between Calculational Methods for the Criticality Safety Analysis of Spent Fuel Storage Pool with Burnup Credit

이창건; 전병진; 노희천researcher, NUCLEAR ENGINEERING AND TECHNOLOGY , v.18, no.1, pp.17 - 26, 1986-01

139
A development of a quantitative situation awareness measurement tool: Computational Representation of Situation Awareness with Graphical Expressions (CoRSAGE)

Yim, Ho Bin; Lee, Seung Min; Seong, Poong-Hyunresearcher, ANNALS OF NUCLEAR ENERGY, v.65, pp.144 - 157, 2014-03

140
A DIAGNOSTIC EXPERT SYSTEM FOR THE NUCLEAR-POWER-PLANT BASED ON THE HYBRID KNOWLEDGE APPROACH

YANG, JO; Chang, Soon-Heungresearcher, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.36, no.6, pp.2450 - 2458, 1989-12

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