김성중 프로필 사진

김성중

Kim, Sung Joong

원자력공학과

공과대학

Web Of Science Scopus ORCID

연구분야

  • Nuclear Safety, 
  • Nuclear Thermal-Hydraulics, 
  • Small Modular Reactor, 
  • 원자력 안전, 
  • 원자로 열수력, 
  • 중소형원전

자료 필터

자료유형

발행연도

2012 ~ 2026
2012 2026

키워드

언어

전체 226건 중 41번부터 50번까지의 결과를 표시합니다.

2023
Article

Development of Simulation Technique for Crust Formation calculation using Rigid Body Dynamics Model in Moving Particle Semi-implicit

  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

MELCOR Analysis of Core Coolability by Flooding Safety System Applicable for i-SMR

  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Assessment of Helium Bubbling Effect in terms of Natural Circulation Performance by Using Experiment and CFD

  • Choi, Wonjun ; 
  • Park, Jae Hyung ; 
  • Lee, Juhyeong ; 
  • Lim, Jihun ; 
  • Cho, Yunsik ; 
  • ... Kim, Sung Joong ; 
  • 외 3명
  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Investigation for Effective Flow Path Designed for Flooding Safety System by Using MELCOR code

  • An, Hyo Jun ; 
  • Park, Jae Hyung ; 
  • Son, Chang Hyun ; 
  • Lee, Jeong Ik ; 
  • Kim, Yonghee ; 
  • ... Kim, Sung Joong
  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Feasibility Evaluation of the Passive Molten Salt Fast Reactor (PMFR) Concept: A Parametric Sensitivity Analysis of Helical Coil Heat Exchangers and Supercritical Carbon Dioxide Power Conversion Systems

  • Im, Jihun ; 
  • Park, Jae Hyung ; 
  • Lee, Juhyeong ; 
  • Choi, Won Jun ; 
  • Cho, Yun Sik ; 
  • ... Kim, Sung Joong
  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Physical properties of KCl-UCl3 molten salts as potential fuels for molten salt reactors

  • 2023-04
  • Journal of Nuclear Materials
  • ELSEVIER
2022
Article

Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident

  • 2022-12
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Preliminary Analysis of Helium Bubbling Effect on Two-phase Flow for Passive Molten Salt Fast Reactor (PMFR)

  • Choia, Won Jun ; 
  • Park, Jae Hyung ; 
  • Lee, Juhyeong ; 
  • Lim, Jihun ; 
  • Cho, Yun Sik ; 
  • ... Kim, Sung Joong ; 
  • 외 3명
  • 2022-10
  • Transactions of the Korean Nuclear Society Autumn Meeting
  • 한국원자력학회
Article

CFD Evaluation of Radiative and Natural Convective Conjugate Heat Transfer in the Gap Space between Small Modular Reactor Vessel and Metal Containment during Normal Operation

  • 2022-10
  • Transactions of the Korean Nuclear Society Autumn meeting
  • 한국원자력학회
Article

Preliminary 3-dimensional analysis for natural circulation of PMFR by using OpenFOAM code

  • Lee, Juhyeong ; 
  • Kim, Taeseok ; 
  • Kim, Yonghee ; 
  • Kim, Sangtae ; 
  • Kim, Sung Joong
  • 2022-10
  • Transactions of the Korean Nuclear Society Autumn meeting
  • 한국원자력학회