• 핵의학기술
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• 제19권2호
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• pp.108-111
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• 2015

Purpose Lately, in accordance with the increasing interest about Healthcare accreditation program and International laboratory accreditation scheme, requirements about the instrument quality management are gradually taking shape. In nuclear medicine In vitro laboratory, the most typical instruments are multi detector gamma counter and automatic dispensing system. Each laboratory continue with the quality control adequate for circumstances. The purpose of this study is to application and establish the new Calibrator[I-125]Set which is efficient at standardization of equipment quality management. Materials and Methods Deviation between detectors were measured with 12 solid samples of the Calibrator[I-125]Set. their activities differ from each other by less than 1%. Multi detector gamma counters are GAMMA-10;Shinjin medics. Inc, Goyansi, Korea(Gamma counter A), SR300;Stratec biomedical systems AG, Gewerbestr, Germany(Gamma counter B) and COBRA II; Packard Instrument Co. Inc, Meriden, USA(Gamma counter C). Evaluation of two automatic dispensing system used A, B liquid tracer of the Calibrator[I-125]Set. After dispensing and counting, calculated using the ratio of the measured value and proposed value. We used solution A for 20, 25ul and solution B for 50, 100ul. Method of data analysis and reference range was provided by kit documentation. Furthermore, we could calculate our counter efficiency indirectly. Results The CV(%) of measured values by Gamma counter A, B, C are 0.34, 0.70, 1.30. Calculated value are 1.05314, 2.10419, 4.08485. Provided reference range is less than 3. A dispensing system's calculated values are 0.986, 0.989, 1.023, 1.017 and B are 0.874, 0.725, 1.021, 0.904. Provided reference range is from 0.95 to 1.05. Also, counter's efficiency are 74.18, 72.79, 74.32% at counter A, B, C and efficiency of the one detector counter is 79.26%. Conclusion If using this Calibrator[I-125]Set after verifying whether quality assurance, is applicable to equipment quality management on behalf of the role of gold standard.

• 대한방사성의약품학회지
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• 제8권2호
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• pp.95-101
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• 2022

Microfluidic radioimmunoassay (RIA) platform called µ-RIA spends less reagent and shorter reaction time for the analysis compared to the conventional tube-based radioimmunoassay. This study reported the design of µ-RIA chips optimized for the gamma counter which could measure the small samples of radioactive materials automatically. Compared with the previous study, the µ-RIA chips developed in this study were designed to be compatible with conventional RIA test tubes. And, the automatic gamma counter could detect radioactivity from the ¹²⁵I labeled anti-PSA attached to the chips. Effects of the multi-layer microchannels and two-phase flow in the µ-RIA chips were investigated in this study. The measured radioactivity from the ¹²⁵I labeled anti-PSA was linearly proportional to the number of stacked chips, representing that the radioactivity in µ-RIA platform could be amplified by designing the chips with multi-layers. In addition, we designed µ-RIA chip to generate liquid-gas plug flow inside the microfluidic channel. The plug flow can promote binding of the biomolecules onto the microfluidic channel surface with recirculation in the liquid phase. The ratio of liquid slug and air slug length was 1 : 1 when the ¹²⁵I labeled anti-PSA and the air were injected at 1 and 35 µL/min, respectively, exhibiting 1.6 times higher biomolecule attachment compared to the microfluidic chip without the air injection. This experimental result indicated that the biomolecular reaction was improved by generating liquid-gas slugs inside the microfluidic channel. In this study, we presented a novel µ-RIA chips that is compatible with the conventional gamma counter with automated sampler. Therefore, high-throughput radioimmunoassay can be carried out by the automatic measurement of radioactivity with reduced radiowaste generation. We expect the µ-RIA platform can successfully replace conventional tube-based radioimmunoassay in the future.

• 방사선산업학회지
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• 제6권3호
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• pp.231-237
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• 2012

This paper introduces a gamma-ray measurement system for a transportable tomography which is applicable for an industrial process diagnosis. The gamma-ray measurement system consists of pulse mode operating 72 channel CsI detectors, main AMP-pulse shaper, single channel analyzer, counter and control PC. The CsI crystal is coupled with a PIN diode which is connected to an amplifier and pulse shaper. For a compact design, the amplifier and pulse shaping circuit are included in a single package. 36 sets of CsI detectors are connected to a multi-channel counter through single channel analyzers. A computer controls and collects data from two multi-channel counters. This configuration results in 72 channel counting system in total. The CT rotator and radiation measurement system are controlled by a PC with LabVIEW program. Tomographic data were measured for a phantom by the measurement system and transportable gamma-ray CT. From the experimental data image reconstructions were performed by ML-EM algorithm. The result showed that the CsI detector system can be a suitable component for transportable gamma-ray CT system.

• 대한전자공학회논문지
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• 제8권1호
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• pp.1-8
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• 1971

G-M 계수관을 이용한 beta와 gamma 선에 민감한 survey meter에 관한 연구이다. 이 장치는 완전 transistor화 되어 있으며 건전지로 동작하게 되어 있고 2.5, 25 및 250MR/HR의 3가지의 full-scale meter range를 직독하게 되어 있다. Counting-rate meter 회로를 이루고 있는 collector 결합 단안정 multivibrator와 전원회로의 de-dc 변환로를 이루고 있는 무안정 blocking 발진기의 해석을 하였고 설계식을 유도하였다. G-M 계수관의 분해시간을 높이기 위하여 0.5v 정도의 낮은 전압으로 triggering할 수 있게 설계하였다.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.1036-1042
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• 2020

Fast-Neutron Multiplicity Counter based on Liquid Scintillator Detector can directly measure the fast neutron multiplicity emitted by UO₂ rod. HPGe gamma spectrometer; which has superior energy resolution; is routinely used for the gamma energy spectrum measurement. Combing Fast-Neutron Multiplicity Counter and HPGe γ-spectrometer, the n/γ joint measurement system is developed. The fast neutron multiplicity and gamma energy spectrum of UO₂ rod assemblies under different conditions are measured by the n/γ joint measurement system. The induced fission rate and the ²³⁵U abundance, thereby the ²³⁵U mass; can be obtained for UO₂ rod assemblies. The ²³⁵U mass deviation of the measured value from the reference value is less than 5%. The results show that the n/γ joint measurement system is effective and applicable in the measurement of the ²³⁵U mass in samples.

• 한국세라믹학회지
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• 제31권6호
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• pp.678-684
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• 1994

The surface of alumina is capable of acquiring a change when it is in an aqueous solution. This surface change will have a strong influence on the surrounding ions, particularly those of opposite change known as the counter ions. A site-binding model of the {{{{ gamma }}-alumina/KCl(aq) interface was used to calculated theoretical surface ionization constants and P.Z.C.(Point of zero change) of {{{{ gamma }}-alumina. This paper was carried out to investigate the effect of calcination temperature on the acidic and electrical properties of pure {{{{ gamma }}-alumina prepared by the precipitation method from the Al(NO3)3.9H2O and NH4OH. From the experimental data it was shown that {{{{ gamma }}-alumina have a mainly Br nsted acid site. However, the acidity of {{{{ gamma }}-alumina decreased with increasing calcination temperature at strength Ho +9.3. The surface charge density of {{{{ gamma }}-alumina was increased with electrolyte ionic strength and calcination temperature.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.249-253
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• 2001

Neutron dose assessment in criticality accidents using Whole Body Counter (WBC) was proved to be an effective method as rapid neutron dose estimation at the JCO criticality accident in Tokai-mura. The 1.36MeV gamma-ray of $^{24}Na$ in a body can be detected easily by a germanium detector. The Minimum Detectable Activity (MDA) of $^{24}Na$ is approximately 50Bq for 10miniute measurement by the germanium-type whole body counter at JNC Tokai Works. Neutron energy spectra at the typical shielding conditions in criticality accidents were calculated and the conversion factor, whole body activity-to-organ mass weighted neutron absorbed dose, corresponding to each condition were determined. The conversion factor for uncollied fission spectrum is 7.7 $[(Bq^{24}Na/g^{23}Na)/mGy]$.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.419-424
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• 2004

방사성 폐기물 중에 함유된 핵종 및 방사능을 측정하기 위해서는 여러 가지 방사선 계측기가 이용되고 있다. 본 연구에서는 각각의 핵종에 대하여 측정 가능한 검출기를 선정하고 원전 방사성폐기물 중 방사능을 측정 하기위한 시스템을 구성하였다. 그리고 그 계측 시스템의 바탕 값 및 계측효율을 주기적으로 측정하고 품질관리를 위한 관리도를 작성하여 계측기의 안전성을 확보하고 분석결과에 대한 신뢰도를 향상시키고자 하였다. Gamma spectrometer의 바탕 값 평균은 1.59 cps이었으며 표준 시료에 대한 평균값은 45,248 dps로 거의 대부분의 측정값이 $2{\sigma}$ 이내에서 크게 벗어나지 않음을 나타냈다. Low background ${\alpha}/{\beta}$ counting 시스템의 알파 바탕 값 평균은 0.31 cpm이고 알파선 계측효율은 34.38% 이었으며, 베타 바탕 값은 1.3 cpm이고 베타선 계측효율 46.5% 이었다. 또한 액체섬광계수기는 3H 영역에서 바탕 값이 2.52 cpm, 계측효율 58.5% 이었으며, 14C 영역에서의 바탕 값은 3.31 cpm 이었고 계측효율은 95.6% 이었다. 본 연구에서는 바탕 값 및 계측효율로부터 최소검출방사능을 설정함으로써 시료의 측정 가능한 범위를 구하였다. 측정결과, gamma spectrometer의 최소검출방사능은 3.2 Bq/$m\ell$이었으며, ${\alpha}/{\beta}$counting 시스템의 경우는 알파 및 베타 영역에서 각각 20.5 Bq/$m\ell$, 23.0 Bq/$m\ell$이고 liquid scintillation counter의 경우는 3.8 Bq/$m\ell$로 나타났다.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2014년도 제46회 동계 정기학술대회 초록집
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• pp.191.1-191.1
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• 2014

Crystallization has become the most popular technique for the separation of enantiomers since the Pasteur's discovery. To investigate mechanism of crystallization of chiral molecules, it is necessary to study self-assembled structures on two-dimensional surface. Here, we have studied two-dimensional self-assembled structures of an unnatural amino acid, (S)-${\beta}$-methyl naphthalen-1-${\gamma}$-aminobutyric acid (${\gamma}^2$-1-naphthylalanine) on Au(111) surface at 150 K using scanning tunneling microscopy (STM). At initial stage, we found two chiral honeycomb structures which are counter-clockwise and clockwise configurations in one domain. The molecules are arranged around molecular vacancies, dark hole. By further increasing the amounts of adsorbed ${\gamma}^2$-1-naphthylalanine, a well-ordered square packed structure was observed. In addition, we found the other structure that molecules were trapped in the pore of the hexagonal molecular assembly.

• 전기전자학회논문지
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• 제21권4호
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• pp.408-411
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• 2017

본 논문에서는 중성자, 감마선, 엑스선 등의 방사선을 측정하는 통합 제어 시스템을 제안한다. 제안하는 시스템은 원격 또는 네트워크상으로 측정 및 분석한 데이터를 디스플레이를 통해 모니터링 및 제어할 수 있는 장비로서, 현장에 가지 않고도 시스템 각 구성 부분의 상태를 보고 변경하여 원격으로 감시 및 관리할 수 있다. 제안하는 시스템은 감마선/엑스선 센서부, 중성자 센서부, 주제어 임베디드 시스템부, 전용 디스플레이 장치 및 GUI부, 원격 UI부 등으로 구성된다. 감마선/엑스선 센서부는 NaI(Tl) Scintillation Detector를 사용하여 저준위의 감마선 및 엑스선을 측정한다. 중성자 센서부는 Proportional Counter Detector(저준위 중성자)와 Ion Chamber Type Detector(고준위 중성자)를 사용하여 중성자를 측정한다. 주제어 임베디드 시스템부는 방사선을 검출하여 초단위로 샘플링하고 누적된 펄스 및 전류값에 대한 방사선량으로 변환한다. 전용 디스플레이 장치 및 GUI부는 방사선 측정 결과와 변환된 방사선량 및 방사능량 측정 수치를 출력하고, 사용자에게 제어 조건 설정 및 검출부에 대한 캘리브레이션 기능을 제공한다. 원격 UI부는 측정된 값들을 취합, 저장하여 원격 감시 시스템에 전달한다. 제안된 시스템의 성능을 평가하기 위하여 공인시험기관에서 실험한 결과는 중성자 검출부는 ${\pm}8.2%$ 이하의 측정 불확도가 측정되었고, 감마선, 엑스선 검출부는 7.5%이하의 불확도가 측정되어 국제 표준인 ${\pm}15%$ 이하에서 정상동작 됨이 확인되었다.