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김태완 증명사진

  • 이름김태완
  • 주전공원자력안전공학, 열유체공학
  • 담당과목원자력공학개론, 원자력안전공학, 에너지안전공학, 신뢰성공학, 재난위험성평가
  • 전화번호032-835-8082
  • E-mail taewan.kim@inu.ac.kr
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학       력
2005.02.25 서울대학교  공학박사
2000.02.26 서울대학교  공학석사
1998.02.26 서울대학교  공학사
연구실적
<논문> 
Feasibility Study of Condensation Heat Exchanger with Helical Tubes for a Passive Auxiliary Feedwater System, International Journal of Applied Engineering Research , 제12권(집) , 제6호 , PP.940~944 , 2017.04.21
Development of effective thermal conductivity models for Reserve Shutdown Control fuel block of prismatic HTGR for hydrogen production, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY , 제42권(집) , PP.18614~18625 , 2017.04.18
Application of Dynamic Probabilistic Safety Assessment Approach for Accident Sequence Precursor Analysis: Case Study for Steam Generator Tube Rupture, Nuclear Engineering and Technology , 제49권(집) , 제2호 , PP.306~312 , 2017.03.30
Analysis of errors of commission for a CE type plant with the advanced control room in the full power condition, ANNALS OF NUCLEAR ENERGY , 제105권(집) , PP.184~195 , 2017.03.15
Extending SBO coping capability: An improved auxiliary feedwater system, PROGRESS IN NUCLEAR ENERGY , 제95권(집) , PP.40~47 , 2016.11.18
A dynamic event tree informed approach to probabilistic accidentsequence modeling: Dynamics and variabilities in medium LOCA, RELIABILITY ENGINEERING & SYSTEM SAFETY , 제142권(집) , PP.78~91 , 2015.05.05
Verification of SAMG entry condition for APR1400, ANNALS OF NUCLEAR ENERGY , 제75권(집) , PP.404~412 , 2015.01.01
Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation, NUCLEAR ENGINEERING AND DESIGN , 제264권(집) , PP.153~160 , 2013.11.01
Improvement of core effective thermal conductivity model of GAMMA plus code based on CFD analysis, ANNALS OF NUCLEAR ENERGY , 제59권(집) , PP.159~168 , 2013.09.01
Effect of longitudinal pitch on convective heat transfer in crossflow overin-line tube banks, ANNALS OF NUCLEAR ENERGY , 제57권(집) , PP.209~215 , 2013.07.01
Quantitative evaluation of change in core damage frequency by postulatedpower uprate: Medium-break loss-of-coolant-accidents, ANNALS OF NUCLEAR ENERGY , 제47권(집) , PP.69~80 , 2012.12.01
Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facilityincluding uncertainty evaluation, NUCLEAR ENGINEERING AND DESIGN , 제249권(집) , PP.97~103 , 2012.08.01
Analysis of Void Fraction Distribution and Departure fromNucleate Boiling in Single Subchannel and Bundle GeometriesUsing Subchannel, System, and ComputationalFluid Dynamics Codes, Science and Technology of Nuclear Installations , 제2012권(집) , 2012.07.20
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