• 해양환경안전학회지
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• 제20권6호
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• pp.760-767
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• 2014

본 연구에서는 길이가 다른 장방형 실린더 사이에서 발생하는 제트류가 후류에 미치는 영향을 알아보기 위해 회류수조에서 PIV기법을 사용하여 실험을 실시하였다. 장방형 실린더의 높이(h)와 실린더 사이의 간격(gap)은 10mm이며 폭(B)은 300mm로 하였다. 유동방향의 모델의 길이(L)는 30mm, 60mm, 90mm 및 120mm를 각각 적용하였으며, 모델의 높이(H=30mm)를 기준으로 길이의 비가 1, 2, 3,및 4이다. 유입유동은 조류의 수심에 따른 차이를 감안하여 모델의 높이(H)를 기준으로 $Re=1.4{\times}10^4$, $Re=2.0{\times}10^4$, $Re=2.9{\times}10^4$를 각각 적용하였으며. 유동계측을 위한 영역은 실린더 후방으로 모델 높이의 5배까지 설정하였다. 실험결과 유속이 증가함에 따라 와의 크기가 후류영역으로 증가하며, 근접 후류에서는 장방형 구조물일수록 관통류의 속도성분이 증가하는 특성을 나타냈다. 또한 후류로 갈수록 속도결손은 유입유동이 증가할수록 종횡비가 작은 경우에 크게 나타났다.

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.531-544
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• 2009

This paper is intended to provide key issues and current research outcomes on accelerator-based Boron Neutron Capture Therapy (BNCT). Accelerator-based neutron sources are efficient to provide epithermal neutron beams for BNCT; hence, much research, worldwide, has focused on the development of components crucial for its realization: neutron-producing targets and cooling equipment, beam-shaping assemblies, and treatment planning systems. Proton beams of 2.5 MeV incident on lithium target results in high yield of neutrons at relatively low energies. Cooling equipment based on submerged jet impingement and micro-channels provide for viable heat removal options. Insofar as beam-shaping assemblies are concerned, moderators containing fluorine or magnesium have the best performance in terms of neutron accumulation in the epithermal energy range during the slowing-down from the high energies. NCT_Plan and SERA systems, which are popular dose distribution analysis tools for BNCT, contain all the required features (i.e., image reconstruction, dose calculations, etc.). However, detailed studies of these systems remain to be done for accurate dose evaluation. Advanced research centered on accelerator-based BNCT is active in Korea as evidenced by the latest research at Hanyang University. There, a new target system and a beam-shaping assembly have been constructed. The performance of these components has been evaluated through comparisons of experimental measurements with simulations. In addition, a new patient-specific treatment planning system, BTPS, has been developed to calculate the deposited dose and radiation flux in human tissue. It is based on MCNPX, and it facilitates BNCT efficient planning based via a user-friendly Graphical User Interface (GUI).