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 81번부터 90번까지의 결과를 표시합니다.

2020
Article

Development of the thermal performance model using temperature gradient analysis for optimized design of steam surface condenser

  • Shin, Doyoung ; 
  • Jeon, Joongoo ; 
  • Kim, Taeseok ; 
  • Park, Jae Hyung ; 
  • Kim, Sung Joong
  • 2020-12
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Semi-mechanistic prediction of spatial variation of local critical heat flux along a slightly inclined downward-facing surface

  • 2020-12
  • International Communications in Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

SMART with Trans-Critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 1: System design

  • 2020-12
  • Annals of Nuclear Energy
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Improved prediction model for H-2/CO combustion risk using a calculated non-adiabatic flame temperature model

  • 2020-12
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower

  • Na, Min Wook ; 
  • Shin, Doyoung ; 
  • Park, Jae Hyung ; 
  • Lee, Jeong Ik ; 
  • Kim, Sung Joong
  • 2020-05
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Nano/microscale roughness control of accident-tolerant Cr- and CrAl-coated surfaces to enhance critical heat flux

  • 2020-02
  • Applied Thermal Engineering
  • PERGAMON-ELSEVIER SCIENCE LTD
2019
Article

Oxidation effect on pool boiling critical heat flux enhancement of Cr-coated surface for accident-tolerant fuel cladding application

  • 2019-12
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Identification of hydrogen flammability in steam generator compartment of OPR1000 using MELCOR and CFX codes

  • 2019-12
  • Nuclear Engineering and Technology
  • KOREAN NUCLEAR SOC
Article

Performance criterion of an indirect dry air-cooled condenser for small modular reactor based on pressure transition temperature

  • Shin, Doyoung ; 
  • Na, Min Wook ; 
  • Lee, Jeong Ik ; 
  • Kim, Yonghee ; 
  • Kim, Sung Joong
  • 2019-11
  • International Journal of Energy Research
  • WILEY