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

Showing results 7201 to 7220 of 10364

7201
Preliminary S-CO2 Compressor Design for Micro Modular Reactor

Lee, Jekyoung; Cho, Seong Kuk; Kim, Seong Gu; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12

7202
Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module

Ahn, Mu-Young; Cho, Seung-Yon; Kim, Duck-Hoi; Lee, Eun-Seok; Kim, Hyung-Seok; Suh, Jae-Seung; Yun, Sung-Hwan; et al, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1753 - 1758, 2008-12

7203
Preliminary Safety Assessment for the Disposal of Neutron Activated Concrete Waste

한솔찬; 김태형; 조용흠; 박창제; 윤종일, 2018 한국방사성폐기물학회 추계학술발표회, Korean Radioactive Waste Society, 2018-11-01

7204
Preliminary safety studies of sodium-CO2 heat exchanger in SFR coupled with S-CO2 brayton cycle = 초임계 이산화탄소 브레이튼 싸이클이 연계된 소듐냉각고속로의 소듐-이산화탄소 열교환기 예비 안전성 연구link

Jung, Hwa-Young; 정화영; et al, 한국과학기술원, 2015

7205
Preliminary shielding analysis for the A-BNCT facility

Lee, Eunjoong; Lee, Cheolwoo; Cho, Gyuseong, RAD 2017, Radiation and Applications, 2017-06-13

7206
Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system

Bae, Seong Jun; Lee, Jekyoung; Ahn, Yoonhan; Lee, Jeong-Ik, ANNALS OF NUCLEAR ENERGY, v.75, pp.11 - 19, 2015-01

7207
Preliminary Studies of Na-CO2 Interaction Byproduct Cleaning Agent for SFR coupled to S-CO2 Power Cycle

Jung, Hwa-Young; Lee, Jeong-Ik; Wi, Myung-Hwan; Hong Joo Ahn, ICAPP 2015, American Nuclear Society, 2015-05-03

7208
Preliminary Studies of Na2CO3 Cleaning from Na-CO2 Interaction in S-CO2 Power Cycle coupled to SFR System

Jung, Hwa Young; Lee, Jeong Ik; Wi, Myung Hwan; Ahn, Hong Joo, The Korean Nuclear Society Autumn Meeting, The Korean Nuclear Society, 2014-10-31

7209
Preliminary Studies of Na2CO3 Elimination from Na/CO2 Reaction in S-CO2 Power Cycle coupled to SFR System

Jung, Hwa Young; Lee, Jeong Ik; Wi, Myung Hwan, The Korean Nuclear Society Spring Meeting, The Korean Nuclear Society, 2014-05-29

7210
Preliminary studies of ocean smart construction and safety enhancement

Kim, Min-gil; Kim, Seong-Gu; Woo, Il-guk; Han, Jeong-Hoon; Lee, PhillSeung; Lee, JeongIk, 2013 International Congress on Advances in Nuclear Power Plants, Organizing Committee of ICAPP2013, 2013-04-14

7211
Preliminary Studies of S-CO2 Critical Flow for Leak Modeling in Sodium-CO2 Heat Exchanger

정화영; 고아름; 위명환; 이정익, the Korean Nuclear Society Spring Meeting(2015), The Korean Nuclear Society, 2015-05-07

7212
PRELIMINARY STUDIES OF SUPERCRITICAL CO2 CYCLE APPLICATION FOR SMALL MODULAR REACTOR WITH A DESALINATION CAPABILITY

Lee, Won Woong; Bae, Seong Jun; Lee, Jeong-Ik, 4th International Technical Meeting on Small Reactors (ITMSR-4), Canadian Nuclear Society, 2016-11-02

7213
Preliminary Studies of Two Fluids Heat Exchangers for S-CO2 Power Conversion Cycle Coupled to SFR

Jung, H-Y; Lee, JeongIk; Wi, M-H; Eoh, J-H; Park, S-M; Ahn, Y, ANS 2013 Winter Meeting, ANS, 2013-11-11

7214
Preliminary Studies of Two-Phase Reactive Process of Sodium-CO2 in S-CO2 Power Conversion Cycle Coupled to SFR System

정화영; 안윤한; 이유호; 이정익, 2013 한국원자력학회 추계학술대회, 한국원자력학회, 2013-10-24

7215
Preliminary studies on the heat exchanger option for S-CO 2 power conversion cycle coupled to water cooled SMR

Ahh,Y; Lee,J; Lee, JeongIk, International Congress on Advances in Nuclear Power Plants 2012 (ICAPP 2012), American Nuclear Society, 2012-06

7216
Preliminary study for a small modular high temperature gas-cooled reactor with gas brayton cycle = 초소형 모듈화 고온가스로를 위한 가스 브레이튼 사이클 예비연구link

Bae, Seong Jun; 배성준; et al, 한국과학기술원, 2015

7217
Preliminary Study for Development of Double Wall Nuclear Fuel Cladding

손성민; 이유호; 이정익, The Korean Nuclear Society Spring Meeting(2015), The Korean Nuclear Society, 2015-05

7218
Preliminary study for the development of PCHE off-design performance model for S-CO2 power conversion cycle of nuclear power plant applications

권진수; 이정익, 한국원자력학회, 2017 추계학술발표회, 한국원자력학회, 2017-10-25

7219
Preliminary Study of 1D Thermal-Hydraulic System Analysis Code Using the Higher-Order Numerical Scheme

Lee, Won Woong; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05

7220
Preliminary study of accident initiator tracking algorithm under loss of coolant accident

김도현; 김민길; 이정익, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-16

Discover

Type

Open Access

Date issued

Subject

. next

rss_1.0 rss_2.0 atom_1.0