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 141번부터 150번까지의 결과를 표시합니다.

2017
Article

Improved safety injection flow map associated with target RCS depressurization to maintain core coolability of OPR1000

  • 2017-06
  • Transactions of the American Nuclear Society
Article

Effects of layer-by-layer assembled PEI/MWCNT surfaces on enhanced pool boiling critical heat flux

  • Seo, Gwang Hyeok ; 
  • Jeong, Uiju ; 
  • Son, Hong Hyun ; 
  • Shin, Doyoung ; 
  • Kim, Sung Joong
  • 2017-06
  • International Journal of Heat and Mass Transfer
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Dynamic wetting characteristics attributable for pool boiling heat transfer of FeCrAl- and Cr-layered vertical tubes

  • 2017-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • Korean Nuclear Society
Article

Analysis of the Mechanistic Critical Heat Flux Models for Downward Facing Boiling Heat transfer

  • Jeong, Uiju ; 
  • Kim, Yeon Soo ; 
  • Kim, Taeseok ; 
  • Kim, Nam Kyung ; 
  • Kim, Sung Joong
  • 2017-05
  • 2017년 한국원자력학회 춘계학술발표회
  • Korean Nuclear Society
Article

Improved Safety Injection Flow Model Associated with Target Depressurization during Severe Accident Management

  • Jeon, Joongoo ; 
  • Choi, Wonjun ; 
  • Kim, Nam Kyung ; 
  • Lee, Yongjae ; 
  • Kim, Sung Joong
  • 2017-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • Transactions of Korean Nuclear Socierty Spring Meeting
Article

Dynamic wetting behavior on oxidized surfaces and its effect on pool boiling critical heat flux

  • 2017-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • Korean Nuclear Society (KNS)
Article

Preliminary Study of Conceptual Design of the ATOM Safety System

  • 2017-05
  • Transactions of Korean Nuclear Socierty Spring Meeting
  • Korean Nuclear Society
Article

MELCOR assessment of sequential severe accident mitigation actions under SGTR accident

  • 2017-05
  • 2017 Transactions of the Korean Nuclear Society Spring Meeting
  • Korean Nuclear Society
Article

Investigation of hydrogen risk in the major containment compartments of OPR1000 using MELCOR code under SBO scenario

  • 2017-05
  • 2017 Transactions of the Korean Nuclear Society Spring Meeting
  • Korean Nuclear Society