• 대한방사선기술학회지:방사선기술과학
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• 제45권1호
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• pp.57-67
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• 2022

CZT detectors, which are compound semiconductors that have been widely used recently for gamma-ray detection purposes, are difficult to detect neutrons because direct interaction with them does not occur unlike gamma-rays. In this paper, a method of detecting and determining energy levels (fast neutrons and thermal neutrons) of neutrons, in addition of identifying energy and nuclide of gamma-rays, and evaluating gamma dose rates using a CZT semiconductor detector is described. Neutrons may be detected by a secondary photoelectric effect or compton scattering process with a characteristic gamma-ray of 558.6 keV generated by a capture reaction (¹¹³Cd + ¹n → ¹¹⁴Cd + 𝛾) with cadmium (Cd) in the CZT detector. However, in the case of fast neutrons, the probability of capture reaction with cadmium (Cd) is very low, so it must be moderated to thermal neutrons using a moderator and the material and thickness of moderator should be determined in consideration of the portability and detection efficiency of the equipment. Conversely, in the case of thermal neutrons, the detection efficiency decreases due to shielding effect of moderator itself, so additional CZT detector that do not contain moderator must be configured. The CZT detector that does not contain moderator can be used to evaluate energy, nuclide, and gamma dose-rate for gamma-rays. The technology proposed in this paper provides a method for detecting both neutrons and gamma-rays using a CZT detector.

• Journal of Radiation Protection and Research
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• 제34권2호
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• pp.65-68
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• 2009

Metal-semiconductor contact is very important for the operating property of semiconductor detector. $Cd_{0.96}$ $Zn_{0.04}$ Te semiconductor crystal was grown with Bridgman method, and the crystal was cut and polished. EPMA (Electron Probe Micro Analyzer) and ICP-MS (Inductively Coupled Plasma Mass Spectrometry) analysis were done to obtain the chemical composition and impurity of the crystal. Metal contact was deposited with thermal evaporator on both sides of the crystal. Detectors with Au/CZT/Au and In/CZT/Au structure were made, and I-V curve and the energy spectrum were measured with the detectors. It could be seen that the detector with the In/CZT/Au structure has superior property than the detector with Au/CZT/Au structure when the crystal resistivity was low. However, the metal contact structure effect becomes low when the crystal resistivity was high.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.81-86
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• 2016

Background: For positron emission tomography (PET) application, cadmium zinc telluride (CZT) has been investigated by several institutes to replace detectors from a conventional system using photomultipliers or Silicon-photomultipliers (SiPMs). The spatial and energy resolution in using CZT can be superior to current scintillator-based state-of-the-art PET detectors. CZT has been under development for several years at the Korea Atomic Energy Research Institute (KAERI) to provide a high performance gamma ray detection, which needs a single crystallinity, a good uniformity, a high stopping power, and a wide band gap. Materials and Methods: Before applying our own grown CZT detectors in the prototype PET system, we investigated preliminary research with a developed discrete type data acquisition (DAQ) system for coincident events at 128 anode pixels and two common cathodes of two CZT detectors from Redlen. Each detector has a $19.4{\times}19.4{\times}6mm^3$ volume size with a 2.2 mm anode pixel pitch. Discrete amplifiers consist of a preamplifier with a gain of $8mV{\cdot}fC^{-1}$ and noise of 55 equivalent noise charge (ENC), a $CR-RC^4$ shaping amplifier with a $5{\mu}s$ peak time, and an analog-to-digital converter (ADC) driver. The DAQ system has 65 mega-sample per second flash ADC, a self and external trigger, and a USB 3.0 interface. Results and Discussion: Characteristics such as the current-to-voltage curve, energy resolution, and electron mobility life-time products for CZT detectors are investigated. In addition, preliminary results of gamma ray imaging using 511 keV of a $^{22}Na$ gamma ray source were obtained. Conclusion: In this study, the DAQ system with a CZT radiation sensor was successfully developed and a PET image was acquired by two sets of the developed DAQ system.

• 분석과학
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• 제35권2호
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• pp.69-81
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• 2022

The method of measuring and classifying the energy category of neutrons directly using raw data acquired through a CZT detector is not satisfactory, in terms of accuracy and efficiency, because of its poor energy resolution and low measurement efficiency. Moreover, this method of measuring and analyzing the characteristics of low-energy or low-activity gamma-ray sources might be not accurate and efficient in the case of neutrons because of various factors, such as the noise of the CZT detector itself and the influence of environmental radiation. We have therefore developed an efficient method of analyzing radiation characteristics using a neutron and gamma-ray analysis algorithm for the rapid and clear identification of the type, energy, and radioactivity of gamma-ray sources as well as the detection and classification of the energy category (fast or thermal neutrons) of neutron sources, employing raw data acquired through a CZT detector. The neutron analysis algorithm is based on the fact that in the energy-spectrum channel of 558.6 keV emitted in the nuclear reaction ¹¹³Cd + ¹n → ¹¹⁴Cd + in the CZT detector, there is a notable difference in detection information between a CZT detector without a PE modulator and a CZT detector with a PE modulator, but there is no significant difference between the two detectors in other energy-spectrum channels. In addition, the gamma-ray analysis algorithm uses the difference in the detection information of the CZT detector between the unique characteristic energy-spectrum channel of a gamma-ray source and other channels. This efficient method of analyzing radiation characteristics is expected to be useful for the rapid radiation detection and accurate information collection on radiation sources, which are required to minimize radiation damage and manage accidents in national disaster situations, such as large-scale radioactivity leak accidents at nuclear power plants or nuclear material handling facilities.

• 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.

• 한국방사선학회논문지
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• 제15권5호
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• pp.741-748
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• 2021

본 연구의 목적은, 몬테 카를로 시뮬레이션 기반 조준기 길이와 검출기 두께 변화에 따른 Cadimium Zinc Telluride (CZT) 와 NaI 검출기 물질을 변화하면서 영상의 질을 비교 평가 해보고자 한다. CZT 와 NaI 검출기 물질 기반 감마카메라를 각각 모사하였고, 조준기 길이는 1, 2, 3, 4, 5, 6 cm, 검출기 두께는 1, 3, 5, 7 mm 로 설정하였다. 1 MBq의 점선원을 이용해 민감도, 4.45, 3.80, 3.15, 2.55 mm 의 지름을 가진 자체 제작한 팬텀을 모사하고, 가장 큰 지름인 4.45 mm 영상에 관심영역을 설정하여 signal to noise ratio (SNR)과 프로파일을 이용하여 각각 획득영상을 분석하였다. 조준기 길이에 따른 CZT 검출기 기반 민감도는 2.3 ~ 48.6 cps/MBq, NaI 검출기 기반 민감도는 1.8 ~ 43.9 cps/MBq 이고, CZT 검출기 기반 팬텀을 활용한 SNR은 3.6 ~ 9.8, NaI 검출기 기반 팬텀 SNR은 2.9~9.5다. 조준기 길이 변화에 따른 프로파일은 조준기의 길이가 증가할수록 영상의 공간 분해능이 향상함을 확인하였다. 또한, 검출기 두께에 따른 CZT 검출기 기반 민감도는 0.04 ~ 0.12 cps/MBq 이고, NaI 검출기 기반 민감도는 0.03 ~ 0.11 cps/MBq 다. CZT 검출기 기반 팬텀 SNR은 7.3~9.8 이며, NaI 검출기 기반 팬텀 SNR은 5.9~9.5다. 또한, 검출기 두께 변화에 따른 프로파일은 검출기 두께가 증가할수록 산란선이 증가함으로써 영상의 공간 분해능이 감소함을 확인하였다. 이 연구데이터를 기반으로 영상 획득 목적에 따라 검출기의 종류와 두께, 조준기의 길이를 선택하여 최고의 영상의 질을 획득할 수 있어야 한다.

• 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.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.87-91
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• 2016

Background: A hand-held detector for an emergency response was developed for nuclide identification and to estimate the information of the ambient dose rate in the scene of an accident as well as the radioactivity of the contaminants. Materials and Methods: To achieve this, the most suitable sensor was first selected as a cadmium zinc telluride (CZT) semiconductor and the signal processing unit from a sensor and the signal discrimination and storage unit were successfully manufactured on a printed circuit board. Results and Discussion: The performance of the developed signal processing unit was then evaluated to have an energy resolution of about 14 keV at 662 keV. The system control unit was also designed to operate the CZT detector, monitor the detector, battery, and interface status, and check and transmit the measured results of the ambient dose rate and radioactivity. In addition, a collimator, which can control the inner radius, and the airborne dust sampler, which consists of an air filter and charcoal filter, were developed and mounted to the developed CZT detector for the quick and efficient response of a nuclear accident. Conclusion: The hand-held CZT detector was developed to make the in-situ gamma-ray spectrometry and its performance was checked to have a good energy resolution. In addition, the collimator and the airborne dust sampler were developed and mounted to the developed CZT detector for a quick and efficient response to a nuclear accident.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.422-424
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• 2002

The accuracy of DXA(Dual Energy X-ray Absorptiometry) highly depends on the detection and separation capability of dual energy X-ray X-ray photons. In addition both of scan time and patient exposure are affected by detection efficiency. A CZT detector with a good energy resolution and high detection efficiency was evaluated for the application of bone densitometry. Its performance was compared to a photomultiplier tube with a NaI(T1) scintillator in terms of energy resolution, detection efficiency and the accuracy of bone mineral density measurement. The comparison study was performed with CZT detector and PM tube using DXA equipments(OSTEO Plus, OSTEO Prima, ISOL Technology). The energy spectrum was acquired using MCA(Multi-Channel Analyzer). The used X-ray energy ranged from 20keV to 86keV. The MCA result of the CZT detector showed a slightly sharper energy spectrum than that of NaI(T1). Detection efficiency of the CZT detector at 59.5keV was 1.4 times better. Remarkably the final results of bone mineral density measurements demonstrate only less than 1% difference. The CZT detector appears to have many benefits for the application of bone densitometry. Its excellent energy resolution can enhance the counting accuracy of dual energy X-ray spectrum. Furthermore its compactness in physical dimension and no cooling requirement will be additional benefits for a more compact and accurate bone densitometer.

• 공업화학전망
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• 제20권2호
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• pp.13-24
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• 2017

태양전지는 온실 가스 감축에 효과가 큰 기후 변화 대응 기술이다. 현재 상업화에 성공한 실리콘 태양전지의 뒤를 이어 박막 태양전지, 페로브스카이트 태양전지 등 차세대 태양전지가 가격과 효율 등을 극복하기 위하여 매우 많이 연구되고 있다. CZT(S,Se) 박막 태양전지는 차세대 태양전지의 유력 후보군인 CIGS, CdTe, 페로브스카이트 태양전지 등에 비해 범용 무독성 원소를 광흡수층으로 사용한다는 장점을 가지고 있지만 아직까지는 이들보다 효율이 낮아 상용화하기에는 많은 문제를 가지고 있다. CZT(S,Se) 박막태양전지의 기본적인 물성, 공정 등을 알아보고 고효율을 달성하는 방법에 대하여 알아보고자 한다.