범용 신틸레이터 감마카메라와 심근전용 반도체 감마카메라의 성능 비교 연구

반영각,황동훈,김정열,강천구,김재삼,Bahn, Young Kag,Hwang, Dong Hoon,Kim, Jung Yul,Kang, Chun Koo,Kim, Jae Sam 대한핵의학기술학회 2016 핵의학 기술 Vol.20 No.2

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. Purpose Recently, Cadmium-zinc-telluride (CZT) semiconductor myocardial SPECT (Single Photon Emission Computed Tomography) has been used myocardial scintigraphy. In this study, the performance of Semiconductor SPECT and conventional SPECT systems was compared by a comprehensive analysis of phantom SPECT images. Materials and Methods Methods: We evaluated the DSPECT CZT SEPCT (Spectrum-dynamic) and INFINA conventional (GE). Physical performance was compared on reconstructed SPECT images from a phantom. Results For count sensitivity on cardiac phantom images ($counts{\cdot}sec^{-1}{\cdot}MBq^{-1}$), DSPECT had a sensitivity of conventional SPECT. This classification was similar to that of myocardial counts normalized to injected activities from phantom images (respective mean values, $counts{\cdot}sec^{-1}{\cdot}MBq^{-1}$: 195.83 and 52.83). For central spatial resolution: DSPECT, 9.47mm; conventional SPECT, 16.90mm. For contrast-to-noise ratio on the phantom: DSPECT, 4.2; conventional SPECT, 3.6. Conclusion The performance of CZT cameras is dramatically higher than that of conventional SPECT. However, CZT cameras differ in that spatial resolution and contrast-to-noise ratio are better with conventional SPECT, whereas count sensitivity is markedly higher with the DSPECT.

동적 심근관류 SPECT에서 심장의 위치 측정방법에 대한 고찰

성지혜,이동훈,김은혜,정우영,Seong, Ji Hye,Lee, Dong Hun,Kim, Eun Hye,Jung, Woo Young 대한핵의학기술학회 2019 핵의학 기술 Vol.23 No.1

Purpose Cadmium-zinc-telluride (CZT) camera with semiconductor detector is capable of dynamic myocardial perfusion SPECT for coronary flow reserve (CFR). Image acquisition with the heart positioned within 2 cm in the center of the quality field of view (QFOV) is recommended because the CZT detector based on focused multi-pinhole collimators and is stationary gantry without rotation. The aim of this study was to investigate the optimal method for measuring position of the heart within the center of the QFOV when performing dynamic myocardial perfusion SPECT with the Discovery NM 530c camera. Materials and Methods From June to September 2018, 45 patients were subject to dynamic myocardial perfusion SPECT with D530c. For accurate heart positioning, the patient's heart was scanned with a mobile ultrasound and marked at the top of the probe where the mitral valve (MV) was visible in the parasternal long-axis view (PLAX). And, the marked point on the patient's body matched with the reference point indicated CZT detector in dynamic stress. The heart was positioned to be in the center of the QFOV in rest. The coordinates of dynamic stress and rest were compared statistically. Results The coordinates of the dynamic stress using mobile ultrasound and those taken of the rest were recorded for comparative analysis with regard to the position of the couch and analyzed. There were no statistically significant differences in the coordinates of Table in & out, Table up & down, and Detector in & out (P > 0.05). The difference in distance between the 2 groups was measured at $0.25{\pm}1.00$, $0.24{\pm}0.96$ and $0.25{\pm}0.82cm$ respectively, with no difference greater than 2 cm in all categories. Conclusion The position of the heart taken using mobile ultrasound did not differ significantly from that of the center of the QFOV. Therefore, The use of mobile ultrasound in dynamic stress will help to select the correct position of the heart, which will be effective in clinical diagnosis by minimizing the image quality improvement and the patient's exposure to radiation. 관상동맥 혈류예비능(CFR)은 관상동맥 협착에 대한 기능적 평가를 하는데 중요한 지표로 사용되고, 허혈성 심장질환(IHD)의 발생을 조기에 진단할 수 있다. 최근 도입된 Discovery NM 530c (D530c) 장비의 구조적 특성으로 인해 동적인 영상 획득이 가능해졌고, 심근 혈류 및 관상동맥 혈류예비능의 측정을 할 수 있게 되었다. D530c 19개 CZT 검출기의 FOV가 교차되는 영역을 QFOV라고 하며, 영상의 질을 위해 QFOV 중앙으로부터 2 cm 이내 심장을 위치시키고 촬영할 것을 권고하고 있다. 동적 심근관류 SPECT 시에 심장의 위치를 선정하기 위한 최적화된 방법을 연구하였다. 심장의 위치를 측정하기 위한 도구로 이동형 초음파를 이용하였다. 환자는 parasternal long-axis view (PLAX) 스캔하였고, 심장 내 구조물이 잘 보이는 탐촉자 지점에 위치를 표시하였다. 환자의 신체에 표시한 지점과 D530c 검출기에 표시된 기준점을 서로 일치시킨 상태에서 약물부하(stress)를 하였고, 방사성동위원소를 순간주사(bolus injection) 하면서 동적 촬영을 시행하였다. 3시간 경과 후, 휴지기(rest) 촬영 시 QFOV 중앙에 심장이 위치하도록 조정하였다. 테이블 및 검출기 위치에 대하여 이동형 초음파를 이용한 dynamic stress와 QFOV 중앙에 위치시킨 rest의 좌표를 비교 분석한 결과, 모든 항목에서 통계적으로 유의한 차이가 없었다(P > 0.05). 이동형 초음파의 이용은 비교적 사용이 간편하면서 시간 단축과 함께 공간의 제약이 없었고, 심장의 정확한 위치 선정에 도움이 되었다. 이는 영상의 질향상과 환자의 불필요한 방사선 피폭을 최소화하고, 심근혈류 및 관상동맥 혈류예비능의 정량적 평가에 도움을 줌으로써 임상적 진단에 효과적일 것으로 사료된다.

CZT검출기를 이용한 CT/SPECT 조합영상시스템

권수일 한국의학물리학회 2002 의학물리 Vol.13 No.4

CdZnTe 검출기를 제작하고 CT/SPECT 조합영상 시스템에 설치하여 엑스선 및 감마선검출기로서의 응용가능성을 타진해 보았다. 검출기의 크기는 10$\times$10$\times$5 ㎣ 이었다. 양극은 4$\times$4 픽셀로 설계하였으며 각 픽셀의 크기는 $1.5\times$l.5 $\textrm{mm}^2$ 이었다. 음극은 Au로 전극을 만들어 주었다. 시스템의 성능을 조사하기 위해서 방사선촬영용 분해능팬텀과 호프만 뇌 팬텀을 사용하였다. X선 영상에서 고광자방출율을 만족시키기 위해서 shapping time은 50ns 로 하었으며, 3$\times$$10^{5}$ counts/s 까지 선형성이 유지되었다. Tc-99m의 140 keV 감마선에 대한 에너지 분해능은 50 ㎱와 2 $\mu\textrm{s}$ shaping time을 걸어주었을 때 각각 10.4%와 5.3%이었다. CT와 SPECT의 공간분해능은 각각 1 mm와 9 mm 이었다. 광피이크 효율은 50 ㎱와 2 $\mu\textrm{s}$일 때 각각 41.0%와 72.5%이었다. We have tested a combined CT/SPECT system with a single CZT detector for x-ray and gamma-ray medical imaging. The size of detector is 10$\times$10$\times$5 ㎣, and the anodes are pixellated as a 4$\times$4 array with a pixel dimension of $1.5\times$1.5 $\textrm{mm}^2$. The cathode was coated with a continuous Au-plated. We have characterized the system performance by scanning a radiographic resolution phantom and the Hoffman Brain phantom. Pulse counting electronics with very short shaping time (50 ㎱) are used to satisfy high photon rates in x-ray imaging, and response linearity up to 3$\times$10$^{5}$ counts per second per detector element is achieved. Energy resolution of 10.4% and 5.3% FWHM at Tc-99m 140 keV peak are obtained for the 50 ㎱ and 2 $mutextrm{s}$ shaping times, respectively. The spatial resolutions of CT and SPECT are about 1mm and 9mm, respectively. Photopeak efficiency of detector systems are 41.0% for 50㎱ and 72.5% for 2 $mutextrm{s}$ shaping time.

Monte Carlo Simulation for Designing a CZT-based Fork Detection System

Wooseong Hong,Geehyun Kim 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2

The detector response was simulated to design a fork detection system for verifying the characteristics of spent fuel. The fork detection system currently used consists of two fission chamber and an ion chamber, and it is nuclear safeguard equipment that measures the gross neutrons and gross gamma rays emitted from the spent fuel assembly to identify the characteristics of the spent fuel and verify the authenticity of the operation history. In order to improve the current fork detection system, we are developing a system that applies CZT, a room temperature semiconductor detector, and a stilbene detector, which is an organic scintillator. Depletion calculations were performed using the ORIGEN code to determine the radiological characteristics emitted from spent nuclear fuel assembly. The flux of radiation emitted from the spent nuclear fuel assembly was calculated by changing the conditions such as initial enrichment, burnup, and cooling time, which are major variables of spent fuel assembly. The calculated result is used as the source term of the particle transport code. Considering the general operating conditions of the pressurized light water reactor, the conditions were changed in the range of 3-5% for initial enrichment and 30-72 GWD/MTU for burnup, and the cooling time was given within 10 years. MCNP 6.2, a Monte Carlo simulation code, was used to simulate the detector response to radiation emitted from spent nuclear fuel assembly. According to the shape, size, and position of the CZT detector, the gamma counts incident on the detector were calculated and derived the initial design of our fork detection system.

CZT를 이용한 국내 가압경수로형 원전 냉각재계통 선원 항 분석

강화윤,문진수,강서곤,김정인 대한방사선방어학회 2013 대한방사선방어학회 학술발표회 논문요약집 Vol.2013 No.04

국내원전의 계획예방정비기간 중 CZT를 이용한 신규원전 및 노후원전 1차계통의 핵종분석

강화윤,강서곤,김정인 대한방사선방어학회 2013 대한방사선방어학회 학술발표회 논문요약집 Vol.2013 No.11

CZT 반도체 검출기를 활용한 중성자 및 감마선 측정과 분석 기술에 관한 연구

진동식(Dong-Sik Jin),홍용호(Yong-Ho Hong),김희경(Hui-Gyeong Kim),곽상수(Sang-Soo Kwak),이재근(Jae-Geun Lee) 대한방사선과학회(구 대한방사선기술학회) 2022 방사선기술과학 Vol.45 No.1

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 + 1 n → 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.

Preliminary Research of CZT Based PET System Development in KAERI

조우진,정만희,김한수,김상열,하장호 대한방사선방어학회 2016 방사선방어학회지 Vol.41 No.2

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 ac-quisition (DAQ) system for coincident events at 128 anode pixels and two common cath-odes of two CZT detectors from Redlen. Each detector has a 19.4×19.4×6 mm3 volume size with a 2.2 mm anode pixel pitch. Discrete amplifiers consist of a preamplifier with a gain of 8 mV·fC-1 and noise of 55 equivalent noise charge (ENC), a CR-RC4 shaping amplifier with a 5 μs 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 reso-lution, and electron mobility life-time products for CZT detectors are investigated. In ad-dition, preliminary results of gamma ray imaging using 511 keV of a 22Na 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.

Preliminary Research of CZT Based PET System Development in KAERI

Jo, Woo Jin,Jeong, Manhee,Kim, Han Soo,Kim, Sang Yeol,Ha, Jang Ho The Korean Association for Radiation Protection 2016 방사선방어학회지 Vol.41 No.2

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.

Effect of Temperature on the Performance of a CZT Radiation Detector

박세환,J. H. Ha,J. H. Lee,H. S. Kim,Y. H. Cho,S. D. Cheon,홍덕균 한국물리학회 2010 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.56 No.4

CdZnTe(CZT) is a promising material for X-ray and -ray detectors. The metal contact on the detector could determine, to a large degree, the performance of the detector. We investigate the dependency of the detector performance on the metal-semiconductor contact at various temperatures. CZT resistive detectors (Pt/CZT/Pt and Au/CZT/Au structure) and a CZT Schottky detector (In/CZT/Au structure) were used in our work. The gold contact was deposited with an electroless deposition method, and the indium contact was made with an evaporation method. The I-V curve and the -ray energy spectrum were measured for each detector at various detector temperatures. The detector temperature was varied from -5 ℃ to 50 ℃. The CZT Schottky detector was seen to a more stable detector performance with changing temperatures.