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 31번부터 40번까지의 결과를 표시합니다.

2024
Article

Vertical-length effect on dropwise condensation heat transfer at low heat flux - Part I: Experimental study

  • 2024-06
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

A machine learning informed prediction of severe accident progressions in nuclear power plants

  • 2024-06
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Performance evaluation of an improved pool scrubbing system for thermally-induced steam generator tube rupture accident in OPR1000

  • 2024-04
  • Nuclear Engineering and Technology
  • 한국원자력학회
Article

[ICAPP 2023] strategic analysis on sizing of flooding valve for successful accident management of small modular reactor

  • An, Hyo Jun ; 
  • Park, Jae Hyung ; 
  • Song, Chang Hyun ; 
  • Lee, Jeong Ik ; 
  • Kim, Yonghee ; 
  • ... Kim, Sung Joong
  • 2024-03
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Residual-based physics-informed transfer learning: A hybrid method for accelerating long-term CFD simulations via deep learning

  • 2024-03
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor

  • Choi, Won Jun ; 
  • Park, Jae Hyung ; 
  • Lee, Juhyeong ; 
  • Im, Jihun ; 
  • Cho, Yunsik ; 
  • ... Kim, Sung Joong ; 
  • 외 1명
  • 2024-03
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

A machine learning diagnosis of the severe accident progression

  • 2024-01
  • Nuclear Engineering and Design
  • Elsevier BV
2023
Article

Parametric study of molten core concrete interaction and assessment of corium coolability in the light of MCCI experiments

  • Hengra, Nasir Hayat ; 
  • Song, Chang Hyun ; 
  • Kim, Sung Joong ; 
  • Ilyas, Muhammad
  • 2023-12
  • Progress in Nuclear Energy
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Effects of Truly Optimized PWR Lattice core design on Reactor Power and Critical Heat Flux in a Natural Circulation Small Modular Reactor

  • Park, Jae Hyung ; 
  • Kim, Nam Gook ; 
  • Im, Jihun ; 
  • An, Hyo Jun ; 
  • Kim, Sung Joong
  • 2023-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Analysis of natural circulation characteristics of passive molten salt fast reactor by using OpenFOAM simulation

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