• Journal of Radiopharmaceuticals and Molecular Probes
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• v.8 no.2
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• pp.113-118
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• 2022

Gadolinium neutron capture therapy (Gd-NCT) is a precision radiation therapy that kills cancer cells using the neutron capture reaction that occurs when ¹⁵⁷Gd hits thermal neutrons. ¹⁵⁷Gd has the highest thermal neutron capture cross section of 254,000 barns among stable isotopes in the periodic table. Another stable isotope, ¹⁵⁵Gd, also has a high thermal neutron trapping area (~ 60,700 barns), so gadolinium that exists in nature can be used as a Gd-NCT drug. Gd-NCT is a mixed kinetic energy of low-energy and high-energy ionizing particles, which can be uniformly distributed throughout the tumor tissue, thereby solving the disadvantage of heterogeneous dose distribution in tumor tissue. The Gd complexes of small-sized molecule are widely used as contrast agents for magnetic resonance imaging (MRI) in clinical practice. Therefore, these compounds can be used not only for diagnosis but also therapy when considering the concept of Gd-NCT. This multifunctional trial can look forward to new medical advance into NCT clinical practices. In this review, we introduce gadolinium compounds suitable for Gd-NCT and describe the necessity of image guided Gd-NCT.

• Journal of Radiopharmaceuticals and Molecular Probes
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• v.8 no.1
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• pp.17-23
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• 2022

Boron neutron capture therapy is a precision treatment technology that selectively destroys only tumor cells by irradiating thermal neutrons after accumulating boron drugs in tumor cells. Brain tumor is difficult to diagnose and treat due to the low permeability and targeting of drugs caused by the blood-brain-barrier. Crossing the BBB is essential for drug delivery to the brain. In this study, we designed and synthesized a novel compound incorporating benzothiazole to develop a boron drug with high BBB permeability and selectivity for brain tumor cells. In addition, their potential as a BNCT drugs was evaluated.

• Nuclear Engineering and Technology
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• v.52 no.9
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• pp.2072-2077
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• 2020

The purpose of this study was to demonstrate the feasibility of sensing changes in a tumor during boron neutron capture therapy (BNCT) using a Monte Carlo simulation tool. In the simulation, an epi-thermal neutron source and a water phantom including boron uptake regions (BURs) were simulated. Moreover, this simulation also included a detector for positron emission tomography (PET) scanning and an adaptively-designed collimator (ADC) for PET. After the PET scanning of the water phantom, including the 511 keV source in the BUR, the ADC was positioned in the PET's gantry. Single prompt gamma rays were collected through the ADC during neutron irradiation. Then, single prompt gamma ray-based tomography images of different sized tumors were acquired by a four-step process. Both the signal-to-noise ratio (SNR) and tumor size were analyzed from each step image. From this analysis, we identified a decreasing trend of both the SNR and signal intensity as the tumor size decreased, which was confirmed in all images. In conclusion, we confirmed the feasibility of sensing changes in a tumor during BNCT using PET and an ADC through Monte Carlo simulation.

• Nuclear Engineering and Technology
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• v.49 no.1
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• pp.189-195
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• 2017

Gel dosimeters have unique advantages in comparison with other dosimeters. Until now, these gels have been used in different radiotherapy techniques as a reliable dosimetric tool. Because dose distribution measurement is an important factor for appropriate treatment planning in different radiotherapy techniques, in this study, we evaluated the ability of the N-isopropylacrylamide (NIPAM) polymer gel to record the dose distribution resulting from the mixed neutron-gamma field of boron neutron capture therapy (BNCT). In this regard, a head phantom containing NIPAM gel was irradiated using the Tehran Research Reactor BNCT beam line, and then by a magnetic resonance scanner. Eventually, the $R_2$ maps were obtained in different slices of the phantom by analyzing T2-weighted images. The results show that NIPAM gel has a suitable potential for recording three-dimensional dose distribution in mixed neutron-gamma field dosimetry.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.427-432
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• 1997

Boron neutron capture therapy(BNCT) is a binary treatment modality that can selectively irradiate tumor tissue. More is known now about the radiation biology of BNCT, which has reemerged as a potentially useful method for preferential irradiation of tumors. We design a square reactor (that can easily be reconfigured into polygonal reactors as the need arises) with four slab type assemblies to produce high quality epithermal neutron beans and thermal neutron beams jot use in neutron capture therapy. With a low operating power of 300kW, the heat generated in the core can be removed by natural convection through a pool of tight water. The proposed design in this study could be constructed for a dedicated clinical BNCT facility that would operate very safely.

• Journal of Radiopharmaceuticals and Molecular Probes
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• v.7 no.1
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• pp.3-10
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• 2021

For successful boron neutron caputre therapy, it is essential to develop a boron drug with a selective accumulation capacity for tumors. In particular, in order to apply boron neutron caputre therapy to brain tumors, drugs with good blood-brain barrier penetration are required. In this study, two low-molecular-weight boron compounds were introduced as brain tumor boron neutron caputre therapy drugs, and their physical and biological efficacy were evaluated. Among them, B2 showed good blood-brain barrier permeability and a high brain/blood ratio. From these results, it is expected that B2 can be used as a useful boron drug for boron neutron caputre therapy in brain tumors.

• Bulletin of the Korean Chemical Society
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• v.32 no.6
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• pp.2139-2142
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• 2011

• Proceedings of the Korean Society of Medical Physics Conference
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• 2006.08a
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• pp.131-131
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• 2006

• Proceedings of the Korean Society of Medical Physics Conference
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• 1999.11a
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• pp.62-65
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• 1999

• Proceedings of the Korean Society of Medical Physics Conference
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• 1999.11a
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• pp.58-61
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• 1999