• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2852-2859
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• 2020

This paper deals with the simulation-based design optimization and experimental validation of the characteristics of an in-core silver Self-Powered Neutron Detector (SPND). Optimized dimensions of the SPND are determined by combining Monte Carlo simulations and analytical methods. As a first step, the Monte Carlo transport code MCNPX is used to follow the trajectory and fate of the neutrons emitted from an external source. This simulation is able to seamlessly integrate various phenomena, including neutron slowing-down and shielding effects. Then, the expected number of beta particles and their energy spectrum following a neutron capture reaction in the silver emitter are fetched from the TENDEL database using the JANIS software interface and integrated with the data from the first step to yield the origin and spectrum of the source electrons. Eventually, the MCNPX transport code is used for the Monte Carlo calculation of the ballistic current of beta particles in the various regions of the SPND. Then, the output current and the maximum insulator thickness to avoid breakdown are determined. The optimum design of the SPND is then manufactured and experimental tests are conducted. The calculated design parameters of this detector have been found in good agreement with the obtained experimental results.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1871-1877
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• 2023

The main goal of the coordinated project development of therapeutic radiopharmaceuticals of Y-90 and Re-188 is to exploit advancements in radionuclide production technology. Here, direct and indirect production methods with medium reactor and cyclotron are compared to evaluate derived neutron flux and production yield. First, nano-sized ¹⁸⁶W and ⁸⁹Y specimens are suspended in water in a quartz vial by FLUKA simulation. Then, the solution is irradiated for 4 days under 9E+14 n/cm2/s neutron flux of reactor. Also, a neutron activator including three layers-lead moderator, graphite reflector, and polyethylene absorbent- is simulated and tungsten target is irradiated by 60 MeV protons of cyclotron to generate induced neutrons for ¹⁸⁸W and ⁹⁰Sr production via neutron capture. As the neutron energy reduced, the flux gradually increased towards epithermal range to satisfy (n/2n,γ) reactions. The obtained specific activities at saturation were higher than the reported experimental values because the accumulated epithermal flux and nano-sized specimens influence the outcomes. The beta emitters, which are widely utilized in brachytherapy, appeal an alternative route to locally achieve a rational yield. Therefore, the proposed method via neutron activator may ascertain these broad requirements.

• 대한전자공학회논문지SD
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• 제48권12호
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• pp.82-90
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• 2011

저전력 전류-모드 신호처리를 위해 새로운 AB급 전류 감산기와 이를 이용한 노튼(Norton) 증폭기를 설계하였다. 전류 감산기는 트랜스리니어 셀(translinear cell), 2개의 전류 미러, 그리고 공통-이미터 증폭기로 구성되었다. 전류 감산의 원리는 트랜스리니어 셀로 입력되는 두 전류의 차가 전류 미러에 의해 얻어지고 이 전류는 공통-이미터 증폭기에 의해 ${\beta}$배 증폭되는 것이다. 노튼 증폭기는 설계한 AB급 전류 감산기와 광대역 전압 버퍼(buffer)로 구성되었다. 시뮬레이션 결과 전류 감산기는 $20{\Omega}$의 입력 저항, 50배의 전류 증폭도, $i_{IN1}$ > $i_{IN2}{\geq}4I_B$의 전류 입력 범위를 갖고 있다는 것을 확인하였다. 노튼 증폭기는 ${\pm}2.5V$ 공급전압에서 312MHz의 단위-이득 주파수, 130dB의 트랜스래지스턴스(transresistance), 4mW의 소비전력은 갖고 있다.

• 한국재료학회지
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• 제14권8호
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• pp.542-546
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• 2004

We report a new fabrication process for high performance triode type CNT field emitters and their superior electrical properties. The CNT-based triode-type field emitter structure was fabricated by the conventional semiconductor processes. The keys of the fabrication process are spin-on-glass coating and trim-and-leveling of the carbon nanotubes grown in trench structures by employing a chemical mechanical polishing process. They lead to strong adhesion and a uniform distance from the carbon nanotube tips to the electrode. The measured emission property of the arrays showed a remarkably uniform and high current density. The gate leakage current could be remarkably reduced by coating of thin $SiO_{2}$ insulating layer over the gate metal. The field enhancement factor(${\beta}$) and emission area(${\alpha}$) were calculated from the F-N plot. This process can be applicable to fabrication of high power CNT vacuum transistors with good electrical performance.

• 한국정보디스플레이학회:학술대회논문집
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• 한국정보디스플레이학회 2003년도 International Meeting on Information Display
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• pp.1021-1023
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• 2003

We studied field-emission characteristics of CNTs under various pre-treatment with $NH_{3}$ plasma on the substrate. The turn-on electric field is the lowest value and field enhancement factor (${\beta}$) is he highest value in CNTs pre-treated by $NH_3$ plasma (80 W and 5 min). The field-emission property of CNTs grown on the Ta substrate is slightly better than on the W substrate.

• 한국진공학회:학술대회논문집
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• 한국진공학회 1999년도 제17회 학술발표회 논문개요집
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• pp.73-73
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• 1999

A large area negative metal ion beam source is developed. Kinetic ion beam of the incident metal ions yields a whole nucleation and growth phenomena compared to the conventional thin film deposition processes. At the initial deposition step one can engineer the surface and interface by tuning the energy of the incident metal ion beams. Smoothness and shallow implantation can be tailored according to the desired application process. Surface chemistry and nucleation process is also controlled by the energy of the direct metal ion beams. Each individual metal ion beams with specific energy undergoes super-thermodynamic reactions and nucleation. degree of formation of tetrahedral Sp3 carbon films and beta-carbon nitride directly depends on the energy of the ion beams. Grain size and formation of polycrystalline Si, at temperatures lower than 500deg. C is obtained and controlled by the energy of the incident Si-ion beams. The large area metal ion source combines the advantages of those magnetron sputter and SKIONs prior cesium activated metal ion source. The ion beam source produces uniform amorphous diamond films over 6 diameter. The films are now investigated for applications such as field emission display emitter materials, protective coatings for computer hard disk and head, and other protective optical coatings. The performance of the ion beam source and recent applications will be presented.

• 한국전기전자재료학회논문지
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• 제20권8호
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• pp.661-665
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• 2007

This paper presents the electrical properties of SiGe HBTs designed with bottom collector and single metal layer structure for RF power amplifier. Base layer was formed with graded-SiGe/Si structures and the collector place to the bottom of the device. Bottom collector and single metal layer structures could significantly simplify the fabrication process. We studied about the influence of SiGe base thickness, number of emitter fingers and temperature dependence $(<200^{\circ}C)$ on electrical properties. The feasible application in $1{\sim}2GHz$ frequency from measured data $BV_{CEO}{\sim}10V,\;f_T{\sim}14GHz,\;{\beta}{\simeq}110,\;NF{\sim}1dB$ using packaged SiGe HBTs. We will discuss the temperature dependent current flow through the e-b, b-c junctions to understand stability and performance of the device.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2007년도 하계학술대회 논문집 Vol.8
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• pp.187-187
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• 2007

This paper presents the electrical properties of SiGe HBTs designed with bottom collector and single metal layer structure for RF power amplifier. Base layer was formed with graded-SiGe/Si structures and the collector place to the bottom of the device. Bottom collector and single metal layer structures could significantly simplify the fabrication process. We studied about the influence of SiGe base thickness, number of emitter fingers and temperature dependence (< $200^{\circ}C$) on electrical properties. The feasible application in 1~2GHz frequency from measured data $BV_{CEO}$ ~10V, $f_r$~14 GHz, ${\beta\simeq}110$, NF~1 dB using packaged SiGe HBTs. We will discuss the temperature dependent current flow through the e-b, b-c junctions to understand stability and performance of the device.

• Nuclear Medicine and Molecular Imaging
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• 제40권2호
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• pp.90-95
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• 2006

Neuroendocrine tumors (NETs) consist of a heterogeneous group of tumors that are able to uptake neuroamine and/or specific receptors, such as somatostatin receptors, which can play important roles of the localization and treatment of these tumors. When considering therapy with radionuclides, the best radioligand should be carefully investigated. $^{131}I$-MIBG and beta-particle emitter labeled somatostatin analogs are well established radionuclide therapy modalities for NETs. $^{111}In,\;^{90}Y\;and\;^{177}Lu$ radiolabeled somatostatin analogues have been used for treatment of NETs. Further, radionuclide therapy modalities, for example, radioimmunotherapy, radiolabeled peptides such as minigastrin are currently under development and in different phases of clinical investigation. for all radionuclides used for therapy, long-term and survival statistics are not yet available and only partial tumour responses have been obtained using $^{131}I$-MIBG and $^{111}In$-octreotide. Experimental results using $^{90}Y$-DOTA-lanreotide as well as $^{90}Y-DOTA-D-Phe1-Tyr^3-octreotide$ and/or $^{177}Lu-DOTA-Tyr^3-octreotate$ have indicated the possible clinical potential of radionuclides receptor-targeted radiotherapy it may be hoped that the efficacy of radionuclide therapy will be improved by co-administration of chemotherapeutic drugs whose antitumoral properties may be synergistic with that of irradiation.

• 한국의학물리학회지:의학물리
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• 제10권1호
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• pp.1-7
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• 1999

본 연구에서는 $\beta$선 방출 동위원소들 중에서 $^{32}$P으로부터 방출되는 $\beta$선에 의한 홉수선량 분포를 방사선원의 형태와 기하학적인 조건을 달리하여 컴퓨터를 이용한 모사실험을 통해 예측함으로써 balloon catheter 및 radioactive stent의 이용과 관련된 정보를 얻고자한다. $^{32}$p로부터 방출된 $\beta$선이 인체내에서 에너지를 전달하는 과정에 대한 모사실험은 EGS4 code system 을 이용하여 수행되었다. 인체내의 방사선 흡수선량은 선원의 형태와 위치를 고려하여 축방향과 반경방향으로 등간격으로 나누어 각 격자에서 계산되었다. $^{32}$P 에서 방출되는 $\beta$선 에너지는 Coulomb 포텐셜에 대한 Dirac방정식의 해를 이용하여 계산된 $\beta$선 스펙트럼의 결과를 사용하여 무작위로 선정되었다. 체적 선원과 표면선원에서 시료 표면으로부터 반경방향으로 깊이 0.5 mm내에 있는 표적체에서의 선량률은 각각 12.133 cGy/s per GBq (0.449 cGy/s per mCi, uncertainty: 1.51%)와 24.732 cGy/s per GBq (0.915 cGy/s per mCi, uncertainty: 1.01 %)이다. 선량률은 시료표면으로부터 축방향과 반경방향으로의 거리에 따라 감소한다. 본 연구 결과를 근거로하여 balloon catheter 및 radioactive stent에 $^{32}$P 핵종을 사용할 때 치료선량을 20 Gy로 할 경우 치료에 적합한 초기 방사능량은 각각 29.69 mCi(치료시간을 3분으로 제한할 때) 와 1.2278 $\mu$Ci (영구삽입)로 계산되었다. 또한 원통형 체적선원과 표면선원에 대하여 초기방사능의 크기를 1 mCi/ml의 방사능 체적 밀도와 0.1 mCi/$cm^2$의 방사능 면 밀도로 나타내었을 때 각 표적체에서의 흡수선량률을 계산하였다. 통일한 값의 방사능 체적 밀도와 방사능 면 밀도는 크기가 다른 모델에 대해서 비슷한 크기의 홉수선량을 유도하므로 $^{32}$p 방사선원의 초기 방사능 체적 밀도와 초기 방사능 면 밀도를 알고 있을 때 본 연구의 계산 결과를 이용하면 직경과 길이가 다른 $^{32}$P 핵종의 원통형 모델 주위의 홉수선량 분포를 쉽게 계산할 수 있다.