http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
정세환(S. H. Jeong),허훈(H. Huh),이상훈(S. H. Lee),서기석(K. S. Seo),조천형(C. H. Cho) 한국소성가공학회 2010 한국소성가공학회 학술대회 논문집 Vol.2010 No.10
This paper is concerned with the dynamic material properties of stainless steels. The effects of strain rate on dynamic flow stress, work hardening characteristics, strain rate sensitivity and elongation to the failure are evaluated under wide range of strain rate. Strain rate effects on the material properties are also investigated. Tensile tests are conducted with 5 kinds of stainless steels; SA-B193 B7, SA-182 F304, SA-350 LF3, SA-240 316L, SUS304. Tensile tests have been performed with the variation of strain rate from 0.001/sec to 100/sec. Quasi-static tensile tests are conducted with INSTRON tensile test machine. Tensile tests at the strain rate of 0.1/sec~100/esc are performed with HSMTM(high speed material testing machine).
김형진(H. Kim),이동규(D.G. Lee),강경욱(G.U. Kang),조천형(C.H. Cho),권오준(O.J. Kwon) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.2
When spent fuel assemblies from the reactor of nuclear power plants(NPPs) are transported, the assemblies are exposed to short-term operations that can affect the peak cladding temperature of spent fuel assemblies. Therefore, it needs to perform the analysis of heat transfer on spent fuel dry cask during the operation. For 3 dimensional computational fluid dynamnics(CFD) simulation, it is proposed that the short-term operation is divided into three processes: Wet, dry, and vacuum drying condition. The three processes have different heat transfer mode and medium. Metal transportation cask, which is Korea Radioactive Waste Agency(KORAD)’s developing cask, is evaluated by the methods proposed in this work. During working hours, the boiling at wet process does not occur in the cask and the peak cladding temperatures of all processes remain below 400℃. The maximum peak cladding temperature is 173.8℃ at vacuum drying process and the temperature rise of dry, and vacuum drying process occurs steeply.
FLUENT를 활용한 콘크리트 건식 저장용기 공기유로 내부 유동장 해석
강경욱(G.U. Kang),김형진(H.J. Kim),조천형(C.H. Cho) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.2
This study investigated natural convection flow behavior in airflow path designed in concrete dry storage cask to remove the decay heat from spent nuclear fuels. Using FLUENT 16.1 code, thermal analysis for natural convection was carried out for three dimensional, 1/4 symmetry model under the normal condition that inlet ducts are 100% open. The maximum temperatures on other components except the fuel regions were satisfied with allowable values suggested in nuclear regulation-1536. From velocity and temperature distributions along the flow direction, the flow behavior in horizontal duct of air inlet and outlet duct, annular flow-path and bent pipe was delineated in detail. Theses results will be used as the theoretical background for the composing of airflow path for the designing of passive heat removal system by understanding the flow phenomena in airflow path.