김성중 프로필 사진

김성중

Kim, Sung Joong

공과대학

원자력공학과

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 101번부터 110번까지의 결과를 표시합니다.

2019
Article

Computational Study of Lean Limit Flames in Hydrogen Mixtures to Investigate Flame Propagation Characteristics

  • 2019-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • Korean Nuclear Society
Article

A Comparative Study of Flammability Limit Models for H2/CO Mixture on the Applicability of Severe Accident Conditions

  • 2019-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
Article

Development of CNAFT model for lower flammability limits of hydrogen mixtures for severe accident analysis code in nuclear power plant

  • 2019-04
  • Proceedings of the ninth international seminar on fire and explosion hazards
  • Peter the Great St. Petersburg Polytechnic University
Article

Application of time-dependent growing mesh for crud growth simulation in single rod scale

  • Cho, Yun Sik ; 
  • Son, Hong Hyun ; 
  • Han, Jong Hoon ; 
  • Kim, Sung Joong ; 
  • Park, Byung Gi ; 
  • 외 2명
  • 2019-03
  • International Conference on Nuclear Engineering, Proceedings, ICONE
  • American Society of Mechanical Engineers (ASME)
Article

Experimental study of saturated pool boiling heat transfer with FeCrAl- and Cr-layered vertical tubes under atmospheric pressure

  • 2019-01
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Local heat transfer characteristics of natural circulation flow inside an 8 x 8 partial spent fuel assembly under dry storage

  • 2019-01
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
2018
Article

Meso-scale multi-physics full coupling within porous CRUD deposits on nuclear fuel

  • Park, Byung Gi ; 
  • Seo, Seungjin ; 
  • Kim, Sung Joong ; 
  • Kim, Ji Hyun ; 
  • Choi, Sungyeol
  • 2018-12
  • Journal of Nuclear Materials
  • ELSEVIER SCIENCE BV
Article

Subcooling effect on boiling heat transfer of inclined downward-facing surface under low flow and pressure

  • 2018-12
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

A semi-mechanistic model to predict spatial variation of critical heat flux on an inclined surface facing downward

  • 2018-11
  • International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting
  • American Nuclear Society
Article

Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation

  • 2018-11
  • Annals of Nuclear Energy
  • PERGAMON-ELSEVIER SCIENCE LTD