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김승필 ( Kim Seungpil ),신명수 ( Shin Myoungsu ),손동성 ( Sohn Dong-seong ),권혁주 ( Kwon Hyukjoo ) 한국구조물진단유지관리공학회 2019 한국구조물진단유지관리공학회 학술발표대회 논문집 Vol.23 No.1
This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental puncture events. Finite element analyses were conducted according to the accident conditions in NUREG-1536 and RG 7.8, which specify 1-m parallel and vertical drops on a rigid rod that has 15-cm diameter and 20-cm height. We focused on the safety evaluation of the cask body, baskets, and canister based on ASME BPVC Section III, and evaluated whether these elements would undergo excessive fracture or puncture.
Dy<sub>2</sub>O<sub>3</sub>-TiO<sub>2</sub> 산화물의 소결성 및 소결체 특성에 관한 연구
김한수,정창용,김시형,이병호,이영우,손동성,이상현,Kim, Han-Soo,Joung, Chang-Yong,Kim, Si-Hyung,Lee, Byoung-Ho,Lee, Young-Woo,Sohn, Dong-Seong,Lee, Sang-Hyun 한국세라믹학회 2002 한국세라믹학회지 Vol.39 No.11
산화물 제어봉 물질로서 $Dy_xTi_yO_z$ 소결체를 powder process에 의해 제조하였다. $Dy_2O_3+TiO_2$ 혼합분말의 소결성과 고용체의 상을 TMA와 XRD로써 각각 분석하였으며, 소결체의 비열과 열확산계수를 측정하여 열전도도를 구하였다. $Dy_xTi_yO_z$에서 Dy의 함량에 따라 소결성과 밀도가 변하였고 $3\;g\;Dy/cm^3\;Dy_xTi_yO_z$의 경우 $1580{\circ}C$의 소결온도에서 용융이 일어났다. $4.00\;g\;Dy/cm^3$ 소결체에는 $Dy_2TiO_5+Dy_2Ti_2O_7$의 두 상이 존재하며 $4.54\;g\;Dy/cm^3$의 경우 $Dy_2TiO_5$의 단일 상만이 존재하는 결과를 보였다. $Dy_xTi_yO_z$의 열전도도는 $25~600{\circ}C$ 범위에서 온도에 따라 큰 변화가 없으며 $1600{\circ}C$ 소결체가 1.69∼1.78 W/mK, 1550$^{\circ}C$ 소결체의 경우에는 1.49~1.55 W/mK이었다. .$Dy_xTi_yO_z$ pellets were fabricated as a reactor control material by the powder process. Sinterability of $Dy_2O_3+TiO_2$ mixtures and phases of solid solutions were analyzed by using TMA and XRD, respectively. The thermal conductivity of .$Dy_xTi_yO_z$ pellet was determined from the measurement data of the specific heat and the thermal diffusivity of the pellet. The sinterability and the sintered density varied as a function of Dy content in $Dy_xTi_yO_z$. The pellet of $3\;g\;Dy/cm^3\;Dy_xTi_yO_z$ melted in the sintering temperature of $1580{\circ}C$. There were two phases of $Dy_2TiO_5+Dy_2Ti_2O_7$ and a single phase of $Dy_2TiO_5$ for the pellet that has the Dy content of .$4.00\;g\;Dy/cm^3$ and .$4.54\;g\;Dy/cm^3$, respectively. The thermal conductivity of $Dy_xTi_yO_z$ was nearly constant in the temperature range of $25~600{\circ}$. It was 1.69~1.78 W/mK for the pellet sintered in .$1600{\circ}$ and 1.49~1.55 W/mK for the pellet sintered in $1550{\circ}$.
내지진용 리드스위치를 이용한 일체형원자로용 위치지시기 개발
유제용(Je-Yong Yu),김지호(Ji-Ho Kim),허형(Hyung Huh),최명환(Myoung-Hwan Choi),손동성(Dong-Seong Sohn) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.11
The reed switch position transmitter (RSPT) is used as a position indicator for the control rod in commercial nuclear power plants made by ABB-CE. But this position indicator has some problems when directly adopting it to the integral reactor. The Control Element Drive Mechanism (CEDM) for the integral reactor is designed to raise and lower the control rod in steps of 2㎜ in order to satisfy the design features of the integral reactor which are the soluble boron free operation and the use of a nuclear heating for the reactor start-up. Therefore the resolution of the position indicator for the integral reactor should be achieved to sense the position of the control rod more precisely than that of the RSPT of the ABB-CE. This paper adopts seismic resistance reed switches to the position indicator in order to reduce the damages or impacts during the handling of the position indicator and earthquake.
영구자석 노화에 따른 제어봉 위치지시기의 성능변화 예측
유제용(Je-Yong Yu),김지호(Ji-Ho Kim),허형(Hyung Huh),최명환(Myoung-Hwan Choi),손동성(Dong-Seong Sohn) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.11
The Control Element Drive Mechanism (CEDM) for the integral reactor is designed to raise and lower the control rod in steps of 2㎜ in order to satisfy the design features of the integral reactor which are the soluble boron free operation and the use of a nuclear heating for the reactor start-up. The actual position of the control rod could be achieved to sense the magnet connected to the control rod by the position indicator around the upper pressure housing of CEDM. It is sufficient that the actual position information of control rod at 20㎜ interval from the position indicator is used for the core safety analysis. As the magnet moves upward along the position indicator assembly from the bottom to the top in the upper pressure housing, the output voltage increases linearly step-wise at 0.2VDC increments. Between every step there are transient areas which occur by a contact closing of three reed switches which is the 2-3-2 contact closing sequence. In this paper the output voltage signal corresponding to the position of control rod was estimated on the 2-1-2 contact closing sequence due to the aging of the magnet.