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배황,전지한,윤은구,정영종,임성원,박현식 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.2
The natural circulation phenomena occurring in fully integrated nuclear reactors are associated with aunique formation mechanism. The phenomenon results from a structural feature of these reactorsinvolving upward flow from the core, located in the central-bottom region of a single vessel, anddownward flow to the steam generator in the annulus region. In this study, to understand the naturalcirculation in a single vessel involving a multi-layered flow path, single-phase and two-phase naturalcirculation tests were performed using the SMART-ITL facility, and validation analysis of the TASS/SMR-Scode was performed by comparing the corresponding test results. Three single-phase natural circulationtests were sequentially conducted at 15%, 10%, and 5% of full-scaled core-power without RCP operation,following which a two-phase natural circulation test was successively conducted with an artificialdischarge of coolant inventory. The simulation capability of the TASS/SMR-S code with respect to thenatural circulation phenomena was validated against the test results, and somewhat conservative butreasonably comparative results in terms of overall thermalhydraulic behavior were shown
모체태아의학 : OB-02 ; 고주파 자궁근종용해술 후 임신3분기 진통없이 발생한 자연자궁파열 1예
고정화,이세진,전지한,나성훈,황종윤 대한산부인과학회 2014 대한산부인과학회 학술대회 Vol.100 No.-
자궁파열은 드물게 발생하지만 발생할 경우 치명적인 합병증으로 모성과 태아의 질병 이환율 및 사망률이 매우 높아 신속한 진단과 처치를 필요로 한다. 최근 본원에서는 21년, 19년전 만삭정상분만 2회 하였고, 이번 임신 5년전 개인산부인과병원에서 복강경하 고주파 자궁근종용 해술 1회 시행받은 과거력이 있는 산과력 2-0-1-2의 42세 경산모에서 임신 36주 3일에 진통없이 갑자기 발생한 자궁파열 및 혈복강 증례를 경험하였고, 신속한 진단 및 처치로 산모 및 태아 모두 건강하게 퇴원하여 이를 보고하는 바이다.
박군철(Goon-Cherl Park),전지한(Ji-Han Chun) 대한기계학회 2009 大韓機械學會論文集B Vol.33 No.9
This paper introduces the current nuclear experimental research activities in KAERI, the unique nuclear research institute in Korea, and the universities in Korea to solve and assess the issues which have been faced in the design of new reactors such as APR1400, SMART, GEN-IV reactors as well as fusion reactor. Also the experimental evaluations of safety for operating nuclear plants have been presented. The nuclear thermalhydraulic experiments performed in such organizations are classified the fundamental test, the separated effect test, and the integral effect test with ATLAS and SNUF. Introduction is deployed according to institutes. Finally, the future works and the direction of research voyage in the nuclear thermal-hydraulic field were suggested.