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

Showing results 3181 to 3200 of 10268

3181
Development of An Amorphous Silicon Flat-Panel Detector for Digital Radiography

Cho, Gyuseong; Kim, HJ; Choi, JH, 대한의용생체공학회 춘계학술대회, pp.167 - 169, 2002

3182
Development of an analytical method for pump-induced pulsating pressure in a pressurized water reactor = 가압경수로에서의 펌프에 의한 맥동압력 해석방법 개발link

Cheong, Jong-Sik; 정종식; et al, 한국과학기술원, 2000

3183
Development of an analytical tilt algorithm = 해석적인 방법에 의한 틸트 계산 알고리즘의 개발link

Hah, Chang-Ju; 하창주; et al, 한국과학기술원, 1987

3184
Development of an applicator for endometrial cancer treatment using a miniature X-ray tube = 초소형 X-선관을 이용한 자궁내막암 치료용 어플리케이터 개발link

Lee, Juhyuk; Cho, Sung Oh; et al, 한국과학기술원, 2018

3185
Development of an artificial neural network model for on-line thermal margin estimation of a nuclear reactor core = 원자로심의 가동중 열여유도 평가를 위한 인공 신경회로망 모델의 개발link

Kim, Hyun-Koon; 김현군; et al, 한국과학기술원, 1992

3186
Development of an ASIC for personal dosimeters using a CsI (TI) based spectroscopy sensor

Yoo, H; Cho, Gyuseong, International Soc Design Conference, International Soc Design Conference, 2016-10-24

3187
Development of an Automated Computer Based Procedure Using Fuzzy Colored Petri Nets for Nuclear Power Plants

Lee, Seung Jun; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.86, no.1, pp.21 - 22, 2002-06

3188
Development of an Automated Operating Procedure System using Fuzzy Colored Petri Nets for Nuclear Power Plants

Lee, Seung Jun; Seong, Poong-Hyun, 한국원자력학회 2002 춘계학술대회, pp.95 - 95, 한국원자력학회, 2002-05

3189
Development of an automated operating procedure system using fuzzy colored petri nets for nuclear power plants = FCPN을 이용한 절차서 기반 원자력 발전소 운전 자동화 시스템의 개발link

Lee, Seung-Jun; 이승준; et al, 한국과학기술원, 2002

3190
Development of an Automated Operating Procedure System using Fuzzy Coloreed Petri Nets for Nuclear Power Plants

Lee, Seung Jun; Seong, Poong-Hyun, International Symposium on Future I&C for NPP, pp.249 - 256, 2002-11

3191
Development of an EEG-based human operator’s mental workload evaluation method in NPPs = 뇌파기반의 원자력 발전소 내 인간운전원의 정신적 작업부하 측정방법 개발link

Choi, Moon Kyoung; 최문경; et al, 한국과학기술원, 2016

3192
Development of an EEG-based workload measurement method in nuclear power plants

Choi, Moon Kyoung; Lee, Seungmin; Ha, Jun Su; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.111, pp.595 - 607, 2018-01

3193
DEVELOPMENT OF AN ELECTROSTATIC ACCELERATOR FOR A MILLIMETER-WAVE FREE-ELECTRON LASER

Cho, Sung Oh; LEE, BC; KIM, SK; JEONG, YU; CHOI, BH; LEE, JM; CHUNG, KH, NUCLEAR INSTRUMENTS METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, v.341, no.1-3, pp.55 - 56, 1994-03

3194
Development of an Environmental Radiation Analysis Research Capability in the UAE

Kim, Sung-yeop; Kim, Changkyu; Lee, Kun Jai; Chang, Soon-Heung; Elmasri, Hasna; Beeley, Philip A., 6th International Conference on Radionuclide Metrology Low-Level-Radioactivity Measurement Techniques, 한국표준과학연구원, 2012-09-19

3195
Development of an environmental radiation analysis research capability in the UAE

Kim, Sung-yeop; Kim, Chankyu; Lee, Kun Jai; Chang, Soon-Heung; Elmasri, Hasna; Beeley, Philip A., APPLIED RADIATION AND ISOTOPES, v.81, pp.190 - 195, 2013-11

3196
Development of an Evaluation Method for Nuclear Safety Culture Competency using Social Network Analysis

Han, Sang Min; Seong, Poong-Hyun, ISOFIC 2017, Korean Nuclear Society, 2017-11-28

3197
Development of an Evaluation Method for Team Safety Culture Competencies Using Social Network Analysis

한상민; 김아름; 성풍현, 한국원자력학회 2016 춘계학술대회, 한국원자력학회, 2016-05-13

3198
Development of an Evaluation Method for the Design Complexity of Computer-Based Displays

김형주; 박진균; 이승우; 강현국; 성풍현, 한국원자력학회 2011 추계학술발표대회, 한국원자력학회, 2011-10-27

3199
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

3200
Development of an Expert System (ESRCP) for Failure Diagnosis of Reactor Coolant Pumps

Cheon, Se-Woo; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.22, no.2, pp.128 - 138, 1990

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