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액체금속로 증기발생기에서 대규모 누출 소듐-물 반응 사고시 중후반기 압력거동특성 연구
정지영,어재혁,정경채,김병호,김태준,남호윤,박남국 한국공업화학회 2005 응용화학 Vol.9 No.1
In order to investigate the pressure transient at the later phase of a large leak sodium-water reaction event in KALIMER(Korea Advanced Llquid MEtal Reactor), an experimental study has been carried out. The experiment was performed to simulate the long-term system transient response of a large leak sodium-water reaction event due to double ended guillotine failure of three tubes in a 1/10 scale-down mock-up test facility with sufficient considerations of the quasi-steady state features of the SWR event.
Design of large-scale sodium thermal-hydraulic integral effect test facility, STELLA-2
이제환,어재혁,윤정,손석권,김형모 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.9
The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS. In STELLA-2, the long-term transient behavior after accidents can be observed and the overall safety aspect can also be evaluated. In this paper, the basic design concept from engineering basis to specific design is described. The design was aimed to meet similarity criteria and requirements based on various non-dimensional numbers and the result satisfied the key features to explain the reasoning of safety evaluation. The result of this study was used to construct the facility and the experiment is on-going. In general, the final design meets the similarity criteria of the multidimensional physics inside the reactor pool. And also, for the conservation of natural circulation phenomena, the design meets the similarity requirements of geometry and thermo-dynamic behavior
정지영,어재혁,정경채,김병호,김종만,김태준,박남국 한국공업화학회 2003 응용화학 Vol.7 No.1
Generally, the analysis of a sodium-water reaction (SWR) is classified by two major events. One is the very initial stage of peak pressure and shock wave propagation caused by the reaction itself, and the other is the bulk motion including the mass transfer phase in the quasi-steady state of the reaction period during several second or minute orders after leak initiation. The system dynamic response during a sodium-water reaction event shows very different characteristics between the initial stage and the long-term period. In order to investigate the later phase of a SWR event. the code SELPSTA (Sodium-water reaction Event Later Phase System Transient Analyzer) has been developed and the desing and construction of the test facility has been made.
정지영,어재혁,김태준,정경체,김병호,한도희,박남국 한국공업화학회 2004 응용화학 Vol.8 No.1
In order to investigate the later phase of a sodium-water reaction (SWR) event in KALIMER (Korea Advanced Liquid MEtal Reactor), the code SELPSTA (Sodium-water reaction Event Later Phase System Transient Analyzer) has been developed and an experimeantal study has been carried out for verification of the simple analysis model applied to the code. The 24 data set obtained in the experiment have been pre-analyzed. Comparison of SELPSTA results with experimental data shows fairly good agreement in the transient.
혼합날개를 이용한 6×6 봉다발 부수로에서의 열전달 향상 특성에 관한 실험적 연구
변선준,어재혁,윤정,정지영 한국기계기술학회 2017 한국기계기술학회지 Vol.19 No.5
In the present study, single-phase heat transfer characteristics for downstream flow in the support grid of 6×6 rod bundle were investigated. It has been known that a turbulence generation due to a support grid with split mixing vanes enhances heat transfer in rod bundle but its heat transfer enhancement actually affects to relatively shorter distance. On the other hand, it has been also turned out that a support grid with large scale vortex flow (LSVF) mixing vanes results in heat transfer enhancement to a longer distance. Based on the results of literatre survey, single-phase water heat transfer experiments were performed for Reynolds numbers at around 30,000, and the heat transfer enhancement effect with both i) the split mixing vanes and ii) the LSVF mixing vanes was compared in this study. The key results showed that the effect of heat transfer enhancement in rod bundle region by the split mixing vanes was maintained up to the length of 15Dh behind the spacer grid. For the Reynolds numbers at around 30,000, it was also observed that the effect using the LSVF mixing vanes was stronger at about 3% when compared to the case using the split mixing vanes only for the distance ranging from 1 to 15Dh behind the spacer grid.