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Performance Improvement and Validation of Advanced Safety Injection Tanks
윤영중,주인철,권태순,송철화,Youn, Young Jung,Chu, In-Cheol,Kwon, Tae-Soon,Song, Chul-Hwa Korean Society of Pressure Vessels and Piping 2011 한국압력기기공학회 논문집 Vol.7 No.1
Advanced SITs of the evolutionary PWRs have the advantage that they can passively control the ECC water discharge flow rate. Thus, the LPSI pumps can be eliminated from the safety injection system owing to the benefit of the advanced SITs. In the present study, a passive sealing plate was designed in order to overcome the shortcoming of the advanced SITs, i.e., the early nitrogen discharge through the stand pipe. The operating principle of the sealing plate depends only on the natural phenomena of buoyancy and gravity. The performance of the sealing plate was evaluated using the VAPER test facility, equipped with a full-scale SIT. It was verified that the passive sealing plate effectively prevented the air discharge during the entire duration of the ECC water discharge. Also, the major performance parameters of the advanced SIT were not changed with the installation of the sealing plate.
강경호(Kyoung-Ho Kang),윤영중(Young-Jung Youn),박종국(Jong-Kuk Park),추연준(Yeon-Jun Choo),천세영(Se-Young Chun),송철화(Chul-Hwa Song) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.11
A series of experiments have been performed in a vertical tube of 9.4 ㎜ inner diameter using the Freon, HFC-134a as working fluid medium under the supercritical pressure range. Two kinds of experiments, i.e. steady-state and pressure transient, have been carried out. As for the steady-state heat transfer experiment, the mass flux was in the range between 600 and 2000 ㎏/㎡s and the maximum heat flux was 160 ㎾/㎡. The selected pressures were 4.1, 4.3 and 4.5 ㎫ which correspond to 1.01, 1.06 and 1.11 times the critical pressure, respectively. In the pressure transient experiments, the inlet pressures were varied from 3.8 to 4.5 ㎫ and vice versa in the pressure transient simulations. In this study, heat transfer correlation and criterion for the heat transfer deterioration are suggested under the supercritical pressures. And also heat transfer characteristics during the pressure transient are examined.
박국남(Kook Nam Park),이종민(Jong Min Lee),윤영중(Young Jung Youn),전형길(Hyung Kil June),안성호(Sung Ho Ahn),이기홍(Kee Hong Lee),김영기(Young Ki Kim),케네디(Timothy C. Kennedy) 대한기계학회 2009 大韓機械學會論文集A Vol.33 No.2
The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It consists of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS, which is located inside the pool is divided into 3-parts; the in-pool pipes, the IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.