• Proceedings of the IEEK Conference
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• 2001.09a
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• pp.539-542
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• 2001

본 논문에서는 검출기의 반응 특성을 선형화 모델링 하여 정규화 할 수 있는 방법을 제안한다. 디지털 의료영상 시스템에서 X-선을 검출하는 검출기의 반응 특성이 모든 검출기마다 다르기 때문에 이 특성을 쉽고 빠르게 정규화 하는 방법이 필요하다. 본 논문에서는 균일한 피사체에 X-선 조사량의 비율을 다르게 하여 두 번 찍은 영상으로 검출기의 반응 특성을 정규화 한다. 실험 결과 일정한 두께의 납 평판에 조사량을 달리하여 촬영한 두 개의 결과 영상을 가지고 검출기의 반응 특성을 보정하면 매우 안정된 결과 영상을 얻을 수 있다.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.312-313
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• 2011

• Journal of Radiation Protection and Research
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• v.37 no.1
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• pp.35-40
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• 2012

Several neutron measuring devices were tested under the neutron fields characterized with two distinct kinds of thermal and fast neutron spectrum. These neutron fields were constructed by the mixing of both thermal neutron fields and fast neutron fields. The thermal neutron field was constructed using by a graphite pile with eight AmBe neutron sources. The fast neutron field of 14 MeV was made by a DT neutron generator. In order to change the fraction of fast neutron fluence rate in each neutron fields, a neutron generator was placed in the thermal neutron field at 50 cm and 150 cm from the reference position. The polyethylene neutron collimator was used to make moderated 14 MeV neutron field. These neutron spectra were measured by using a Bonner sphere system with an LiI scintillator, and dosimetric quantities delivered to neutron surveymeters were determined from these measurement results.

• Journal of the Korean Chemical Society
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• v.37 no.4
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• pp.453-461
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• 1993

Detection method was developed using a simply designed photochemical reactor made of teflon coil and low pressure mercury lamp. This method of UV photolysis of analytes followed by UV, fluorescence and electrochemical detection was found to be useful for four thiocarbamates. Analytes eluting from the column are irradiated with a high flux of 254 nm UV light, so that they change to either fluorescent active forms or highly electrochemically sensitive products. Appling this technique to the UV detection, thiocarbamates were converted into long wavelength absorbing products upon UV irradiation. In fluorescence detector four thiocarbamates are not detected at nonirradiated condition but fluorescence signals of MPTC, CPTC photolysates are appeared after irradiation with UV light. The electrochemical detection for the determination of thiocarbamates was enhanced up to 5∼20 fold signal after UV irradiation, compared to that of the nonirradiated. The detection limit of thiocarbamates on electrochemical detector was 13.3∼0.02 ng under pH 7.0, ionic strength $0.5{\times}10^{-2}$ M, phosphate buffer solution. Adducts produced by reaction of photolysates and OPA-MERC in the reaction coil were monitored at 425 nm with fluorescence detector, and one of the photolysates was primary amine.

• Journal of the Institute of Electronics Engineers of Korea SC
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• v.48 no.4
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• pp.102-107
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• 2011

In this paper, a microfluidic array biochip for simultaneously detecting multiple antigen-antibody bindings was designed and implemented. The biochip has the single channel in which microreaction chambers are serially connected, and the antibody-coated microbeads are packed in each microreaction chamber. In addition, the weir structure was fabricated in the microchannel using the gray-scale photolithography in order to trap the microbeads in the microreaction chamber. Three kinds of antibodies were chosen, and the antibodies were immobilized onto the microbeads by the streptavidin-biotin conjugation. In the experiment, as the fluorescence-labeled antigens were injected into the microchannel, the antigen-antibody bindings were completed in 10 minutes. When the solution with multiple antigens was injected into the microchannel, it was observed that the fluorescence intensity increased in only the corresponding microreaction chambers with few non-specific binding. The microfluidic array biochip implemented in this study provides, even with the consumption of tiny amount of sample and fast reaction time to simultaneously detect multiple immunoreactions.

• Proceedings of the Optical Society of Korea Conference
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• 2000.02a
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• pp.12-13
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• 2000

진행파형 광 검출기는 전기적으로 분포된(distributed) 구조이므로, 그 대역폭은 RC 시정수에 의해 제한되기보다는 광 흡수계수와 광과 마이크로파 사이의 진행속도 차에 의해 제한된다$^{(1)(2)}$ . 진행파형 광검출기에서 광과 마이크로파 사이의 속도 부정합이 대역폭에 미치는 영향은 속도 부정합 임펄스 반응(velocity-mismatch impulse response)의 제시를 통해 이미 분석되었다$^{(1)(2)}$ . 그러나, 대역폭에 제한에 큰 영향을 미칠 것이 예상되는 진성 흡수 영역에서의 전송자 표류 시간은 아직 구체적으로 고려되지 않았다. 본 논문에서는 진성 흡수영역에서의 전송자 표류 시간을 고려하였다. 그 전이 시간(transit time)을 고려하기 위해 속도 부정합 임펄스 반응을 수정하여 제시하였다. 새로히 제시된 임펄스 반응은 광 도파로 해석과 진성 영역 분할에 의해 모델화 되었으며, 이 임펄스 반응을 통해 전이 시간과 속도 부정합이 대역폭에 미치는 영향을 살펴보았다. (중략)

• Journal of the Korean Institute of Telematics and Electronics
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• v.4 no.2
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• pp.16-21
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• 1967

This report describes actual fabrication mehod of Li drifted Ge detector. The gamma-ray spectrum from Cl(n, r) reaction measured by this Li drifted Ge detector are also shown. Energy resolution(FWHM) of this Li drifted Ge detector is 4.5KeV at the 122KeV( ), and 10KeV a the 1333KeV( ) respectively.

• Journal of Radiation Protection and Research
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• v.40 no.2
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• pp.79-86
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• 2015

$^3He$ gas has been used for neutron monitors as the neutron converter owing to its advantages such as high sensitivity, good ${\gamma}$-discrimination capability, and long-term stability. However, $^3He$ is becoming more difficult to obtain in last few years due to a global shortage of $^3He$ gas. Accordingly, the cost of a neutron monitor using $^3He$ gas as a neutron converter is becoming more expensive. Demand on a neutron monitor using an alternative neutron conversion material is widely increased. $^{10}B$ has many advantages among various $^3He$ alternative materials, as a neutron converter. In order to develop a neutron converter using $^{10}B$ (actually $B_4C$), we calculated the optimal thickness of a neutron converter with a Monte Carlo simulation using MCNP6. In addition, a neutron converter was fabricated by the Ar sputtering method and the neutron signal detection efficiencies were measured with respect to various thicknesses of fabricated a neutron converter. Also, we developed a 2-dimensional multi-wire proportional chamber (MWPC) for neutron beam profile monitoring using the fabricated a neutron converter, and performed experiments for neutron response of the neutron monitor at the 30 MW research reactor HANARO at the Korea Atomic Energy Research Institute. The 2-dimensional MWPC with boron ($B_4C$) neutron converter was proved to be useful for neutron beam monitoring, and can be applied to other types of neutron imaging.

• Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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• 2007.06a
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• pp.531-531
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• 2007

현재 널리 사용되고 있는 X선 영상 검출기의 문제점을 해결하기 위해 새로운 연구가 활발히 진행되고 있다. 본 논문에서는 새로운 X선 검출기로써의 가능성 제시를 위해 Display용 PDP(Plasma Display panel)를 디지털 X-ray Detector로 적용하기 위한 기본적인 X-ray에 대한 반응성을 검증하였다. PDP의 X-ray Detector로의 사용 가능성을 보기 위하여, 실험에 사용된 panel은 상용화된(commercial) Display용 PDP의 기본적인 구조와 똑같은 구조의 sample을 제작하여 사용하였다. 제작된 panel은 상판에 Substrate glass와 유전체층, 투명전극을 형성하고, 버스 전극층과 MgO층을 형성하였다. 하판에는 격벽을 제작하고 형광체(R.G.B)층을 형성하고, 어드레스 전극을 형성하여 기존의 Display용 PDP와 똑같은 구조를 지니게 하였다. 이렇게 제작된 panel의 X-선 검출기로서의 전기적 특성물 조사하기 위해 누설전류(Dark current), X선 민감도(X-ray sensitivity), 그리고 선형특성(Linearity)을 측정하였다. 측정 결과, 누설전류가 낮고 X-선 검출기로서의 가능성이 충분한 민감도를 보이며, 선형적 특성 또한 우수한 결과를 보이는 등 안정된 전기적 동작특성을 보였다. 이러한 결과로부터 기존에 사용되어오던 디스플레이용 PDP의 구조적 변경을 통하여 상용화된 PDP룰 디지털 X-선 검출기로서의 적용 가능성을 확인할 수 있었다.

• Journal of the Korean Society of Radiology
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• v.10 no.5
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• pp.337-341
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• 2016

We measured the neutron capture cross-section of natural Sm(n,${\gamma}$) reaction in the energy regions from 0.003 to 10 eV. The 46-MeV electron linear accelerator of Research Reactor Institute, Kyoto University was used for generating a continuous neutron source. The neutron time-of-flight method was adopted for energy measurement. An assembly of BGO($Bi_4Ge_3O_{12}$) scintillators composed of 12 pieces of BGO crystals measured prompt gamma rays from Sm(n,${\gamma}$) reaction. The BGO assembly was located at a distance of $12.7{\pm}0.02m$ from the neutron source. In order to determine the neutron flux impinging on the Sm, the $^{10}B(n,{\alpha}{\gamma})^7Li$ standard cross-section were used. Natural Sm(n,${\gamma}$) reaction measurement result of the neutron capture cross-section was compared with the results of evaluation of the BROND-2.2 and the previous experimental data of J. C. Chou and V. N. Kononov.