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 138건 중 71번부터 80번까지의 결과를 표시합니다.

2018
Article

Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress

  • Choi, Wonjun ; 
  • Kim, Taeseok ; 
  • Jeon, Joongoo ; 
  • Kim, Nam Kyung ; 
  • Kim, Sung Joong
  • 2018-08
  • Science and Technology of Nuclear Installations
  • HINDAWI LTD
Article

Efficacy analysis of hydrogen mitigation measures of CANDU containment under LOCA scenario

  • 2018-08
  • Annals of Nuclear Energy
  • PERGAMON-ELSEVIER SCIENCE LTD
Article

Feasibility assessment of air-cooling system as an ultimate heat sink of the atom system

  • Shin, Doyoung ; 
  • Seo, Gwang Hyeok ; 
  • Na, Min Wook ; 
  • Kim, Sung Joong ; 
  • Kim, Yonghee ; 
  • 외 1명
  • 2018-07
  • International Conference on Nuclear Engineering, Proceedings, ICONE
  • American Society of Mechanical Engineers (ASME)
Article

Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident

  • Kim, Taeseok ; 
  • Choi, Wonjun ; 
  • Jeon, Joongoo ; 
  • Kim, Nam Kyung ; 
  • Kim, Sung Joong
  • 2018-07
  • Proceedings of the 26th International Conference on Nuclear Engineering
  • The American Society of Mechanical Engineers
Article

Sensitivity analysis of RCS depressurization strategy under a postulated SGTR accident in OPR1000

  • Choi, Wonjun ; 
  • Kim, Taeseok ; 
  • Jeon, Joongoo ; 
  • Kim, Nam Kyung ; 
  • Kim, Sung Joong
  • 2018-07
  • International Conference on Nuclear Engineering, Proceedings, ICONE
  • American Society of Mechanical Engineers (ASME)
Article

Investigation of flammability of hydrogen gases with diluent gases under severe accident conditions using CNFT model

  • Jeon, Joongoo ; 
  • Kim, Nam Kyung ; 
  • Choi, Wonjun ; 
  • Kim, Taeseok ; 
  • Kim, Sung Joong
  • 2018-07
  • International Conference on Nuclear Engineering, Proceedings, ICONE
  • American Society of Mechanical Engineers (ASME)
Article

Understanding role of flow obstacle on bubble behavior and CHF in two-phase boundary layer flow

  • 2018-05
  • Transactions of the korean nuclear society spring meeting
  • 한국원자력학회
Article

Investigation of downward flow gas mixture in a PAR during SBO using the MELCOR code

  • Kim, Yeon Soo ; 
  • Kim, Nam Kyung ; 
  • Jeon, Joongoo ; 
  • Choi, Wonjun ; 
  • Kim, Sung Joong
  • 2018-05
  • Transactions of Korean Nuclear Society Spring Meeting
  • Transactions of Korean Nuclear Society Spring Meeting
Article

Safety limit estimation of natural circulation loop in EU-APR1400 Ex-vessel core catcher system

  • 2018-05
  • Transactions of the Korean Nuclear Society Spring Meeting
  • 한국원자력학회
2017
Article

PIV Investigation of natural convective flow inside 8×8 partial fuel assembly

  • 2017-11
  • 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017
  • Association for Computing Machinery, Inc