• 공업화학
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• 제28권5호
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• pp.571-575
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• 2017

본 연구에서는 초음파 조사법을 사용하여 cadmium telluride (CdTe) 양자점을 합성하였다. 전구체의 비율과 합성 시간을 주 변수로 하여 그에 따른 CdTe 양자점의 광학적 특성과 구조적 특성을 분석하였다. 모든 cadmium (Cd)과 tellurium(Te) 함량비율의 실험에서 합성 시간이 증가함에 따라 CdTe 양자점의 성장에 의해 밴드갭 감소현상이 관찰되었고, 발광 특성을 확인한 결과 510~610 nm 파장 범위에서 장파장으로 이동함을 보였다. 또한 Te의 비율이 증가함에 따라 장파장이동이 빠르게 일어나는 것을 확인하였다. Photoluminescence (PL) 피크 강도를 확인하였을 때 합성시간이 180 min~240 min 사이에서 가장 높은 강도를 보였다. X-ray diffraction (XRD)와 transmission electron microscopy (TEM)으로 구조적 특성을 확인한 결과 zinc blend 구조의 CdTe 양자점을 나타내었으며, 합성시간이 210 min일 때 양자점의 크기는 약 2.5 nm로 균일하게 분산되어 있었으며 fast fourier transform (FFT) 이미지를 확인한 결과 뚜렷한 결정성을 확인하였다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1718-1733
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• 2023

The virtual Frisch-grid method for room-temperature radiation detectors has been widely used because of its simplicity and high performance. Recently, side electrodes were separately attached to each surface of the detectors instead of covering the entire detector surface with a single electrode. The side-electrode structure enables the measurement of the three-dimensional (3D) gamma-ray interaction in the detector. The positional information of the interaction can then be utilized to precisely calibrate the response of the detector for gamma-ray spectroscopy and imaging. In this study, we developed a 3D position-sensitive 5 × 5 × 12 mm³ cadmium-zinc-telluride (CZT) detector and applied a flattening method to correct detector responses. Collimated gamma-rays incident on the surface of the detector were scanned to evaluate the positional accuracy of the detection system. Positional distributions of the radiation interactions with the detector were imaged for quantitative and qualitative evaluation. The energy spectra of various radioisotopes were measured and improved by the detector response calibration according to the calculated positional information. The energy spectra ranged from 59.5 keV (emitted by ²⁴¹Am) to 1332 keV (emitted by ⁶⁰Co). The best energy resolution was 1.06% at 662 keV when the CZT detector was voxelized to 20 × 20 × 10.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4652-4659
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• 2022

Among the detector materials available at room temperature, thallium bromide (TlBr), which has a relatively high atomic number and density, is widely used for gamma camera imaging. This study aimed to verify the usefulness of TlBr through quantitative evaluation by modeling detectors of various compound types using Monte Carlo simulations. The Geant4 application for tomographic emission was used for simulation, and detectors based on cadmium zinc telluride and cadmium telluride materials were selected as a comparison group. A pixel-matched parallel-hole collimator with proven excellent performance was modeled, and phantoms used for quality control in nuclear medicine were used. The signal-to-noise ratio (SNR), contrast to noise ratio (CNR), sensitivity, and full width at half maximum (FWHM) were used for quantitative analysis to evaluate the image quality. The SNR, CNR, sensitivity, and FWHM for the TlBr detector material were approximately 1.05, 1.04, 1.41, and 1.02 times, respectively, higher than those of the other detector materials. The SNR, CNR and sensitivity increased with increasing detector thickness, but the spatial resolution in terms of FWHM decreased. Thus, we demonstrated the feasibility and possibility of using the TlBr detector material in comparison with commercial detector materials.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4620-4624
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• 2022

Several cadmium zinc telluride (CZT) crystals were fabricated into radiation detectors using methods that included slicing, dicing, lapping, polishing, and chemical etching. A wet passivation with sodium hypochlorite (NaOCl) was then carried out on the Br-etched detectors. The Te-rich layer on the CZT surface was successfully compensated to the Te oxide layer, which was analyzed with X-ray photoelectron spectroscopy data of both a Br-etched crystal and a passivated CZT crystals. We confirmed that passivation with NaOCl improved the transport property by analyzing the mobility-lifetime product and surface recombination velocity. The electrical and spectroscopic properties of large volume detectors were compared before and after passivation, and then the detectors were observed for a month. Both bar and quasi-hemispherical detectors show an enhancement in performance after passivation. Thus, we could identify the effect of NaOCl passivation on large volume CZT detectors.

• 방사선산업학회지
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• 제17권1호
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• pp.119-125
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• 2023

Burnup of spent nuclear fuel should be determined accurately for the safety storage of spent nuclear fuel. In this study, a gamma detection system was developed as a part of basic research to measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibration source. The prototype of the gamma detection system was based on a semiconductor sensor using a CZT (Cadmium Zinc Telluride). For quantitative evaluation, tests were conducted using ¹³⁷Cs, ¹³⁴Cs and ²⁵²Cf calibration source. In the performance evaluation, Its field applicability was verified by assessing the energy resolution, the detection linearity and the shielding attenuation according to the nuclide.

• 방사성폐기물학회지
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• 제22권2호
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• pp.129-137
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• 2024

To non-destructively determine the burnup of a spent nuclear fuel assembly, it is essential to analyze the nuclear isotopes present in the assembly and detect the neutrons and gamma rays emitted from these isotopes. Specifically, gamma-ray measurement methods can utilize a single radiation measurement value of ¹³⁷Cs or measure based on the energy peak ratio of Cs isotopes such as ¹³⁴Cs/¹³⁷Cs and ¹⁵⁴Eu/¹³⁷Cs. In this study, we validated the extent to which the results of gamma-ray measurements using cadmium zinc telluride (CZT) sensors based on ¹³⁷Cs could be accurately simulated by implementing identical conditions on MCNP. To simulate measurement scenarios using a lead collimator, we propose equations that represent radiation behavior that reaches the detector by assuming "Direct hit" and "Penetration with attenuation" situations. The results obtained from MCNP confirmed an increase in measurement efficiency by 0.47 times when using the CZT detector, demonstrating the efficacy of the measurement system.

• 한국정보통신학회논문지
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• 제15권6호
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• pp.1349-1354
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• 2011

본 연구에서는 CdZnS와 CdTe로 구성되는 이종접합 소자를 제작하고 커패시턴스-전압 특성을 조사하였다. CdS/CdTe 접합의 경우, 역방향 바이어스가 증가함에 따라 공핍층의 폭이 커져 커패시턴스 값이 약간 감소하였으나 CdZnS/CdTe 접합에서는 CdTe 박막 내에서의 공핍층 폭이 바이어스에 크게 영향을 받지 않아 커패시턴스 값이 역방향 바이어스에 따라 거의 변화가 없었다. 바이어스 전압을 인가하지 않은 상태에서의 공핍층 폭은 높은 CdZnS 박막의 비저항 및 낮은 캐리어 농도로 인해 CdS/CdTe 접합보다 CdZnS/CdTe 접합에서 보다 큰 값을 나타내었다. CdZnS/CdTe 태양전지의 개방전압은 Zn의 비율이 커짐에 따라 CdZnS 박막과 CdTe 박막의 전자 친화력 차이의 감소로 인하여 크게 증가하였으나, Zn 비율이 0.35 이상인 경우 오히려 감소함을 알 수 있었다. 또한 CdZnS 박막의 높은 비저항이 태양전지의 직렬저항을 상승시켜 전지의 변환 효율은 오히려 감소함을 알 수 있었다.

• 핵의학기술
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• 제20권2호
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• pp.49-53
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• 2016

최근 Cadmium-zinc-telluride (CZT) 반도체를 이용한 심장전용 감마카메라가 심장 핵의학 검사에 사용되고 있다. 본 연구는 기존 NaI(Tl) 신틸레이터를 사용한 감마카메라와 성능을 비교해 보고자 한다. CZT반도체를 사용한 심장전용 감마카메라(DSPECT, Spectrum-dynamic)와 범용 신틸레이터 SPECT 감마카메라(Infinia, GE)를 사용하여 연구를 진행했다. 방사성 동위원소는 $^{99m}TcO^{-4}$를 사용하고, 일반 임상 심장핵의학 검사에 사용된 조건을 실험 조건으로 설정 했다. NEMA 2001, 3 line phantom을 사용하여 반치폭(full width at half maximum, FWHM)을 측정하여 공간분해능(Spatial resolution)을 비교했다. 심장 팬텀을 사용하여 대조도대잡음비(Contrast to noise, CNR)를 비교하여 영상을 평가했다. 그리고 팬텀의 시간 당 MBq당 계수를 측정하여 민감도도 평가했다. NaI (Tl) 신틸레이터를 사용한 범용SPECT 감마카메라와 CZT 반도체를 사용한 심장 전용 감마카메라의 영상평가에서 감도는 $52.83counts{\cdot}sec^{-1}{\cdot}MBq^{-1}$과 $195.83counts{\cdot}sec^{-1}{\cdot}MBq^{-1}$로 나왔고, 공간분해능은 16.90 mm과 9.47 mm로 나왔다. 그리고 대조도대 잡음비는 3.6 과 4.2 로 나왔다. 기존 카메라를 이용한 심장 핵의학 영상과 비교하여 CZT를 사용한 심장 전용 감마카메라는 감도 및 공간분해능, 대조도대잡음비가 기존 감마카메라와 비교하여 월등하여 임상에서 환자의 피폭선량 저감과 검사 시간 단축, 높은 분해능의 영상으로 환자 만족도에 큰 영향을 줄 것으로 사료 된다.

• 대한방사선기술학회지:방사선기술과학
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• 제44권5호
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• pp.459-464
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• 2021

The detector performance is important role in acquiring the gamma rays from patients. Among parameters of detector performances, there is density, which relates to respond to gamma rays. Therefore, we confirm the detection efficiency according to various detector materials based on the density parameter using GATE (geant4 application for emission tomography) simulation tool. The NaI (density: 3.67 g/cm³), CZT (Cadimium Zinc Telluride) (density: 5.80 g/cm³), CdTe (Cadmium Telluride) (5.85 g/cm³), and GAGG (Gadoinium Aluminum Gallium Garnet) (density g/cm³) were used as detector materials. In addition, the point source and quadrant bar phantom, which is modeled for 0.5, 1.0, 1.5, and 2.0 mm thicknesses, were modeled to confirm the quatitative analysis using sensitivity (cps/MBq) and the full width at half maximum (FWHM, mm) at the 2.0 mm bar thickness containing visual evaluation. Based on the results, the sensitivity for NaI, CZT, CdTe, and GAGG detector materials were 0.12, 0.15, 0.16, and 0.18 cps/MBq. In addition, the FWHM for quadrant bar phantom in the 2.0 mm bar thickness is 3.72, 3.69, 3.70, and 3.73 mm for NaI, CZT, CdTe, and GAGG materials, respectively. Compared with performance of detector materials according to density, the high density can improve detection efficiency in terms of sensitivity and mean count. Among these detector materials, the GAGG material is efficient for detection of gamma rays.

• Journal of Radiation Protection and Research
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• 제45권1호
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• pp.35-44
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• 2020

Background: Cadmium zinc telluride (CZT) is a promising material because of a high detection efficiency, good energy resolution, and operability at room temperature. However, the cost of CZT dramatically increases as its size increases. In this study, to achieve a large effective volume with relatively low cost, an array structure comprised of individual virtual Frisch-grid CZT detectors was proposed. Materials and Methods: The prototype consisted of 2 × 2 CZTs, a holder, anode and cathode printed circuit boards (PCBs), and an application-specific integrated circuit (ASIC). CZTs were used and the non-contacting shielding electrode method was applied for virtual Frisch-grid effect. An ASIC was used, and the holder and the PCBs were fabricated. In the current system, because the CZTs formed a common cathode, a total of 5 channels were assigned for data processing. Results and Discussion: An experiment using ¹³⁷Cs at room temperature was conducted for 10 minutes. Energy and timing information was acquired and the depth of interaction was calculated by the timing difference between the signals of both electrodes. Based on obtained three-dimensional position information, the energy correction was carried out, and as a result the energy spectra showed the improvements. In addition, a Compton image was reconstructed using the iterative method. Conclusion: The virtual Frisch-grid CZT detector based on the array structure was developed and the energy spectra and the Compton image were successfully acquired.