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Showing results 1 to 14 of 14

1
A preliminary study on steam generator sizing for the sodium-cooled fast reactor KALIMER-600

권진수; 이정익; 김상지, 2019 한국원자력학회 춘계학술발표회, 한국원자력학회, 2019-05-23

2
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

3
Experimental printed circuit steam generator design for dryout induced thermal fatigue study

권진수; 이정익; 김상지, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-24

4
Experimental Study of Two-Phase Critical Flow for Supercritical CO2 application

김민석; 오봉성; 권진수; 이정익, 2017 한국원자력학회 춘계학술발표회, 한국원자력학회, 2017-05-17

5
Experimental Study on CO2 critical flow comparison with MARS

권진수; 오봉성; 김민석; 김민길; 조재완; Lee, Jeong-Ik, 2016 한국원자력학회 춘계학술발표회, 한국원자력학회, 2016-05-13

6
PCHE off-design performance model for S-CO2 power cycle under SMART condition

권진수; 이정익, 2017 한국원자력학회 춘계학술발표회, 한국원자력학회, 2017-05-17

7
Preliminary Analysis of Steam Rankine Cycle as Power Conversion System of Thermal Energy Storage using Shell and Tube Steam Generator

오승환; 권진수; 이정익, 2019 한국원자력학회 춘계 학술발표회, 한국원자력학회, 2019-05-23

8
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

9
Preliminary Study of Printed Circuit Heat Exchanger (PCHE) for various power conversion systems for SMART

권진수; 백승준; 이정익, 2016 한국원자력학회 추계학술발표회, 한국원자력학회, 2016-10-28

10
Preliminary study of steam cycle layout and modeling for SMR application

이재준; 이원웅; 권진수; 이정익, 2017 한국원자력학회 춘계학술발표회, 한국원자력학회, 2017-05-18

11
Review of compact heat exchangers for supercritical CO2 power system

권진수; 이정익, 2018 한국원자력학회 추계학술발표회, 한국원자력학회, 2018-10-25

12
Study of Critical Flow for Supercritical CO2 Turbomachinery Seal Design

김민석; 배성준; 오봉성; 권진수; 이정익, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17

13
Study of Printed Circuit Steam Generator Numerical Modeling Methodology Using CFD

신성길; 권진수; 이정익, 한국원자력학회 2020 온라인 추계학술발표회, 한국원자력학회, 2020-12-17

14
Validation of KAIST-STA (System Transient Analysis) Code with CO2 Experimental Data under the Trans-critical Operating Condition.

배성준; 권진수; 이정익, 한국원자력학회 2017춘계학술발표회, 한국원자력학회, 2017-05-17

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