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

Showing results 3161 to 3180 of 10267

3161
Development of accelerated PCHE off-design performance model for optimizing power system control strategies in S-CO2 power conversion system of nuclear power plant applications

권진수; 이정익, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17

3162
Development of accelerated PCHE off-design performance model for optimizing power system control strategies in S-CO2 system

Kwon, Jinsu; Lee, Jeong-Ik, 6th International Supercritical Symposium CO2 Power Cycles Symposium, Southwest Research Institute, 2018-03-29

3163
Development of accelerated PCHE off-design performance model for optimizing power system operation strategies in S-CO2 Brayton cycle

Kwon, Jin Su; Bae, Seong Jun; Heo, Jin Young; Lee, Jeong Ik, APPLIED THERMAL ENGINEERING, v.159, 2019-08

3164
Development of accelerated prediction method using artificial neural network for nuclear power plant severe accident application = 원자력 발전소 중대사고 적용을 위한 인공신경망 기반 가속 예측 방법 개발link

Lee, Yeonha; Lee, Jeong Ik; et al, 한국과학기술원, 2022

3165
Development of accelerator beam window cooling configuration

Lee, JeongIk; Cho, JS; Park, BS; Kin, HS, The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Korean Nuclear Society, 2008-10

3166
Development of accident sequence analysis method and operation procedure for success of feed-and-bleed operation under combined accident = 복합사고 상황에서 주입 및 방출 운전의 성공을 위한 사고 시퀀스 분석 방법론 및 운전 절차 개발link

Kim, Bo Gyung; Kang, Hyun Gook; et al, 한국과학기술원, 2016

3167
Development of advanced high strength and high CISCC resistance duplex stainless steels for dry storage canister = 건식저장용기용 고강도 및 고CISCC 저항성 듀플렉스 스테인리스강 개발link

Jeong, Chae Won; Jang, Changheui; et al, 한국과학기술원, 2020

3168
Development of Advanced Operation Validation System Using Support Vector Regression Algorithm

Kim, Seung Geun; Seong, Poong-Hyun, 한국원자력학회 2014 춘계발표대회, 한국원자력학회, 2014-05-29

3169
Development of Advanced Printed Circuit Heat Exchanger Analysis Code for Various Flow Paths

Lee, JeongIk; Son, Seong Min; Lee, You Ho, Korean Nuclear Society Spring Meeting, 한국원자력학회, 2014-05-29

3170
Development of advanced risk informed asset management tool based on system dynamics approach for nuclear power plant = 시스템 다이나믹스를 이용한 원자력발전소의 위험도정보활용 자산관리 도구 개발link

Lee, Gyoung-Cheol; 이경철; et al, 한국과학기술원, 2007

3171
Development of albedo-corrected parameterized equivalence constants for macroscopic depletion in coarse-mesh nodal analysis of nuclear reactors = 원자로심 소격격자 거시연소 해석을 위한 중성자 누설이 보정된 소수군 등가인자 방법론 개발link

Jang, Seongdong; Kim, Yonghee; et al, 한국과학기술원, 2022

3172
Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors

Kim, Hyunmyung; Jang, Hun; Subramanian, Gokul Obulan; Kim, Chaewon; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.507, pp.1 - 14, 2018-08

3173
Development of ambient dose equivalent conversion algorithm using artificial neural network with gamma spectroscopic dosimeter

황지성; 김진환; 박경진; 이민주; 김준혁; 김우섭; 고길영; et al, 한국방사선산업학회, 한국방사선산업학회, 2019-11-06

3174
Development of an Accident Diagnosis System using a Dynamic Neural Network for Nuclear Power Plants

Lee, Seung Jun; Kim, Jong Hyun; Seong, Poong-Hyun, 한국원자력학회 2004 춘계발표회, 한국원자력학회, 2004-05

3175
Development of an advanced annunciator system for nuclear power plants = 원자력 발전소를 위한 개선된 경보 시스템의 개발link

Hong, Jin-Hyuk; 홍진혁; et al, 한국과학기술원, 1996

3176
Development of an advanced human-machine interface for next generation nuclear power plants

Chang, Soon-Heung; Choi, SS; Park, JK; Heo, GY; Kim, HG, RELIABILITY ENGINEERING SYSTEM SAFETY, v.64, no.1, pp.109 - 126, 1999-04

3177
Development of an advanced PFM code for the integrity evaluation of nuclear piping system under combined aging mechanisms = 다양한 열화기구를 고려한 확률론적 파괴 해석 코드 개발을 통한 원전 배관의 건전성 평가link

Datta, Debashis; 다따, 데바시스; et al, 한국과학기술원, 2010

3178
Development of an advanced printed circuit heat exchanger analysis code for realistic flow path configurations near header regions

Son, Seongmin; Lee, Youho; Lee, Jeong Ik, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.89, pp.242 - 250, 2015-10

3179
Development of an AFEN Method Code in cylindrical (r,θ,z) Geometry for Design Analysis of Pebble Bed Modular Reactor

Cho, Nam-Zin; Lee, J.H; Lee, J.J; Kim, DS, Proc. of the Korean Nuclear Society, 2005-05

3180
Development of an aluminide coating layer on Alloy 617 by Al sputtering and inter-diffusion heat treatments

Kim, Dong-Hoon; Sah, Injin; Lee, Ho Jung; Hong, Sunghoon; Jang, Changheui, SURFACE & COATINGS TECHNOLOGY, v.244, pp.15 - 22, 2014-04

Discover

Type

Open Access

Date issued

Subject

. next

rss_1.0 rss_2.0 atom_1.0