CURRENT RESEARCH ON ACCELERATOR-BASED BORON NEUTRON CAPTURE THERAPY IN KOREA

被引:8
|
作者
Kim, Jong Kyung [1 ]
Kim, Kyung-O [1 ]
机构
[1] Hanyang Univ, Dept Nucl Engn, Seoul 133791, South Korea
关键词
Accelerator-based BNCT; Epithermal Neutron; Target System; Beam-shaping Assembly; Treatment Planning System; BTPS; MCNP; NEAR-THRESHOLD; BERYLLIUM TARGET; BEAM DESIGN; BNCT; DOSIMETRY; LI-7(P;
D O I
10.5516/NET.2009.41.4.531
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper is intended to provide key issues and current research outcomes Oil 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 oil 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 I user-friendly Graphical User Interface (GUI).
引用
收藏
页码:531 / 544
页数:14
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