NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 1 to 20 of 4026

1

Development of simplified beam model of a spent nuclear fuel rod

이상훈; BELAL; 장동찬researcher한국원자력학회2018 한국원자력학회 춘계학술발표회, 2018-05-17

2

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

권진수; 이정익researcher한국원자력학회2017 한국원자력학회 춘계학술발표회, 2017-05-17

3

Application of Adjoint Sensitivity Analysis Procedure(ASAP) to Single Phase Thermal-Hydraulic System Analysis Code

김민길; 이원웅; 이정익researcherThe Korean Nuclear SocietyThe Korean Nuclear Society Spring Meeting(2017), 2017-05-17

4

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

김민석; 오봉성; 권진수; 이정익researcher한국원자력학회2017 한국원자력학회 춘계학술발표회, 2017-05-17

5

TRANSIENT SIMULATION OF CRITICAL FLOW WITH THERMAL-HYDRAULIC SYSTEM ANALYSIS CODE FOR SUPERCRITICAL CO2 APPLICATIONS

KIM, MINSEOK; Oh, Bong-seong; Kwon, Jinsu; Jung, Hwa-Young; Lee, Jeong-IkresearcherASMEASME Turbo Expo 2017, 2017-06

6

PRELIMINARY STUDY OF AN INTELLIGENT AUTONOMOUS OPERATION SYSTEM FOR NUCLEAR POWER PLANT WITH THERMAL-HYDRAULIC ANALYSIS CODE

Kim, Min-Gil; Lee, Jeong-IkresearcherANSNURETH-17(2017), 2017-09-03

7

Comparison of CO2 Critical Flow Model Based on Isentropic Flow with Two-phase Flow

김민석; 정화영; 이정익researcher한국원자력학회2017 한국원자력학회 추계학술발표회, 2017-10-25

8

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

김도현; 김민길; 이정익researcher한국원자력학회2018 한국원자력학회 춘계학술발표회, 2018-05-16

9

Comparison of large LWR to SMR under LOCA for future development of autonomous operation algorithm

Kim, Min-Gil; Lee, Jeong-Ikresearcher한국원자력학회2018 한국원자력학회 춘계학술발표회, 2018-05-16

10

EXPERIMENTAL AND NUMERICAL STUDY OF CRITICAL FLOW MODEL DEVELOPMENT FOR SUPERCRITICAL CO2 POWER CYCLE APPLICATION

KIM, MINSEOK; Oh, Bong-seong; Jung, Hwa-Young; Bae, Seong Jun; Lee, Jeong-IkresearcherASMEThe ASME Turbo Expo 2018, 2018-06

11

Comparison the steam Rankine cycle with the supercritical CO2 Brayton cycle as a power conversion system for water-cooled SMR

Kwon, Jinsu; Baik, Seungjoon; Lee, Jeong-IkresearcherANS2016 ANS Winter Meeting & Technology Expo, 2016-11-06

12

Control logic development of KAIST Micro Modular Reactor for marine propulsion

김도규; 오봉성; 이정익researcher한국원자력학회한국원자력학회 2017춘계학술발표회, 2017-05-17

13

STUDY OF S-CO2 POWER CYCLE FOR WATER-COOLED SMR WITH A DESALINATION CAPABILITY

Kwon, Jinsu; Bae, Seong Jun; Heo, Jin Young; Lee, Jeong-IkresearcherANSNURETH-17, 2017-09-03

14

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

권진수; 이정익researcher한국원자력학회한국원자력학회, 2017 추계학술발표회, 2017-10-25

15

Instability Experimental Design of Magnetic Bearing in KAIST Micro Modular Reactor

김도규; 백승준; 이정익researcher한국원자력학회한국원자력학회, 2017 추계학술발표회, 2017-10-25

16

Experimental study of magnetic bearing instability under supercritical CO2 cooled MMR conditions

김도규; 백승준; 이정익researcher한국원자력학회한국원자력학회 2018 춘계학술발표회, 2018-05-16

17

Compensation to Local Residents: Unexpected Survey Results from the Public Deliberation on Shin-Gori Nuclear Reactors No. 5 & 6

김철민; 임만성researcher한국원자력학회한국원자력학회 2018 춘계학술발표회, 2018-05-17

18

Study of Magnetic Bearing Instability Issues in Supercritical CO2 Turbomachinery

Kim, Dokyu; Baik, Seungjoon; Lee, Jeong-IkresearcherThe Clearwater Clean Energy Conference43rd International Technical Conference on Clean Energy, 2018-06-03

19

Public Preferences for the Safety Characteristics of Small Modular Reactor

Kim, Chul Min; Yim, Man-SungresearcherInstitute of Nuclear Materials Management (INMM)INMM 59th Annual Meeting, 2018-07-25

20

Passive Safety Is Not a Panacea: Perception of the Safety Features of Nuclear Power

Kim, Chul Min; Yim, Man-SungresearcherKAISTThe 6th International Conference on Nuclear and Renewable Energy Resources (NURER2018), 2018-10-02

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