• 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.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.379-381
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• 2002

A single CdZnTe detector is tested for suitability in a prototype CT/ SPECT system designed to acquire both emission and transmission data. The detector has the size of 1${\times}$l-cm$^2$ with 4${\times}$4 1.5${\times}$l.5mm$^2$ pixellated anodes. Since the detector is smaller than imaged object, we translated it in an arc centered at the x-ray tube to image larger objects. Pulse counting electronics with very short shaping time (50 ns) 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. The energy resolution of 122-keV gamma-ray is measured to be 14%. We have characterized the system performance by scanning a radiographic resolution phantom .and the Hoffman brain phantom. The spatial resolution of CT and SPECT are about 1 mm and 7 mm, respectively.

• 방사성폐기물학회지
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• 제21권4호
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• pp.543-558
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• 2023

Currently, Japan is undertaking a nationwide project to measure and map radioactive contamination around Fukushima, as part of the efforts to restore normalcy following the nuclear accident. The Japan Atomic Energy Agency (JAEA) manages the Fukushima Environmental Safety Center, located approximately 20 km north of the Fukushima Daiichi nuclear power plant in Minamisōma City, Fukushima Prefecture. In collaboration with the JAEA, this study involved conducting comparison experiments and analyses with radiation detectors in high radiation environments, a challenging task in Korean environments. Environmental radiation surveys were conducted using three types of detectors: CZT, NaI(Tl), and LaBr₃(Ce), across two contaminated areas. Dose rate values were converted using dose rate conversion factors for each detector type, and dose rate maps were subsequently created and compared. The detectors yielded similar results, demonstrating their feasibility and reliability in high radiation environments. The findings of this study are expected to be a crucial reference for enhancing the verification and supplementation of procedures and methods in future radiation measurements and mobile surveys in high-radiation environments, using these three types of radiation instruments.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.275-279
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• 2001

In uranium enrichment plants and nuclear fuel fabrication facilities, exact measurement of fissile isotope enrichment of uranium is required for material accounting in international safeguards inspection as well as process quality control. The purpose of this study was to develop a simple measurement system which can portably be used at nuclear fuel fabrication plants especially dealing with low enriched uranium. For this purpose, a small size CZT (CdZnTe) detector was used, and the detector performance in low uranium gamma/X -rays energy range was investigated by use of various enriched uranium oxide samples. New enrichment measurement technique and analysis method for low enriched uranium oxide, so-called, 'semi-peak ratio technique' was developed. The newly developed method was considered as an alternative technique for the low enrichment and would be useful to account nuclear material in safeguarding activity at nuclear fuel fabrication facility.

• 방사선산업학회지
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• 제18권3호
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• pp.249-253
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• 2024

For the safe management and disposal of spent fuel, it is essential to accurately determine the quantities of nuclides present within the spent fuel. In this study, a Gamma/Neutron detection system was developed as a part of basic research to measure the burnup profile of spent fuel, and a performance was evaluated using major nuclides. The prototype of the Gamma/Neutron detection system consisted of a CZT sensor and a ³He chamber. For quantitative evaluation, studies were conducted using calibrated ¹³⁷Cs, ¹³⁴Cs, ¹⁵⁴Eu and ²⁵²Cf sources. In the performance evaluation, a field applicability was verified by analyzing the detection characteristics according to the nuclide.

• 한국의학물리학회지:의학물리
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• 제27권3호
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• pp.105-110
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• 2016

Sparse angular sampling has been studied recently owing to its potential to decrease the radiation exposure from computed tomography (CT). In this study, we investigated the analytic reconstruction algorithm in sparse angular sampling using the sinogram interpolation method for improving image quality and computation speed. A prototype of the spectral CT system, which has a 64-pixel Cadmium Zinc Telluride (CZT)-based photon-counting detector, was used. The source-to-detector distance and the source-to-center of rotation distance were 1,200 and 1,015 mm, respectively. Two energy bins (23~33 keV and 34~44 keV) were set to obtain two reconstruction images. We used a PMMA phantom with height and radius of 50.0 mm and 17.5 mm, respectively. The phantom contained iodine, gadolinium, calcification, and lipid. The Feld-kamp-Davis-Kress (FDK) with the sinogram interpolation method and Maximum Likelihood Expectation Maximization (MLEM) algorithm were used to reconstruct the images. We evaluated the signal-to-noise ratio (SNR) of the materials. The SNRs of iodine, calcification, and liquid lipid were increased by 167.03%, 157.93%, and 41.77%, respectively, with the 23~33 keV energy bin using the sinogram interpolation method. The SNRs of iodine, calcification, and liquid state lipid were also increased by 107.01%, 13.58%, and 27.39%, respectively, with the 34~44 keV energy bin using the sinogram interpolation method. Although the FDK algorithm with the sinogram interpolation did not produce better results than the MLEM algorithm, it did result in comparable image quality to that of the MLEM algorithm. We believe that the sinogram interpolation method can be applied in various reconstruction studies using the analytic reconstruction algorithm. Therefore, the sinogram interpolation method can improve the image quality in sparse-angular sampling and be applied to CT applications.

• Journal of the Korean Physical Society
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• 제73권9호
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• pp.1393-1398
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• 2018

In conventional single-photon emission computed tomography (SPECT), only the photoelectric events in the detectors are used for image reconstruction. However, if the $^{131}I$ isotope, which emits high-energy radiations (364, 637, and 723 keV), is used in nuclear medicine, both photoelectric and Compton scattering events can be used for image reconstruction. The purpose of our work is to perform simulations for Compton SPECT by using the Geant4 application for tomographic emission (GATE). The performance of Compton SPECT is evaluated and compared with that of conventional SPECT. The Compton SPECT unit has an area of $12cm{\times}12cm$ with four gantry heads. Each head is composed of a 2-cm tungsten collimator and a $40{\times}40$ array of CdZnTe (CZT) crystals with a $3{\times}3mm^2$ area and a 6-mm thickness. Compton SPECT can use not only the photoelectric effect but also the Compton scattering effect for image reconstruction. The correct sequential order of the interactions used for image reconstruction is determined using the angular resolution measurement (ARM) method and the energies deposited in each detector. In all the results of simulations using spherical volume sources of various diameters, the reconstructed images of Compton SPECT show higher signal-to-noise ratios (SNRs) without degradation of the image resolution when compared to those of conventional SPECT because the effective count for image reconstruction is higher. For a Derenzo-like phantom, the reconstructed images for different modalities are compared by visual inspection and by using their projected histograms in the X-direction of the reconstructed images.

• 한국공작기계학회논문집
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• 제11권6호
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• pp.111-117
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• 2002

The high quality and a nearly stoichometric growth of $Cd_{1-y} Zn_y$/Te(y＝0.04) epilayers have been successfully grown on GaAs substrate by hot wall epitaxy (HWE) by optimizing the growth condition including the preheating treatment and Cd reservoir temperature. The relationship between quality and thickness was examined and best value of FWHM from X-ray rocking curve of 121 arcsec are obtained. Also, emission peaks related to the recombination of free excitons such as the ground state and the first excited state were observed in the PL spectrum at 4.2K. The ($A^0$, X) emission related to Cd vacancy and deep level emission was not measured. These results indicated that the grown CZT/GaAs epilayer was high qualify and purity.

• Journal of Radiation Protection and Research
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• 제39권1호
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• pp.54-60
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• 2014

IAEA는 핵물질 계량 관리 검사를 위해 다양한 방사선 검출기를 사용하고 있다. 주로 HPGe, NaI(Tl), CZT 등이 사용되며, 정확한 측정이 요구되는 검사에는 고분해능 HPGe 검출기 활용도가 높다. HPGe 검출기는 추가적인 냉각장치로 인하여 부피가 크고 무거우며, 사용하기 전에 충분히 냉각시켜야 하기 때문에 측정의 준비 시간이 많이 걸린다는 단점이 있다. 이러한 문제점을 해결하기 위해 가볍고 짧은 사용 전 냉각이 요구되는 휴대형 HPGe가 개발되었다. 본 논문은 개발된 휴대형 HPGe 검출기 시제품을 실제 IAEA 사찰 현장에 적용하여 얻은 성능평가 결과를 기술한다. 휴대형 HPGe로 얻은 방사선 스펙트럼은 핵물질 종류와 농축도에 따라 다른 특징을 보였고, 또한 $^{235}U$과 $^{238}U$의 붕괴 계열에서 방출되는 감마선 및 우라늄의 특성 x-선 차이도 확인할 수 있었다. 그리고 휴대형 HPGe 검출기 시제품으로 측정한 농축도는 핵물질 종류에 따라 실제값과 9 ~ 27%의 상대적 오차를 보였다. 휴대형이라는 소형 검출기의 한계 때문에 일부 핵물질은 IAEA에서 요구하는 정확도를 만족시키지 못하는 경우도 있었지만 향후 추가적인 연구의 수행으로 이러한 문제점은 해결 가능할 것으로 판단된다. 본 논문은 새로운 휴대형 HPGe 검출기를 안전조치에 적용한 사례와 측정한 스펙트럼을 농축도 분석 코드로 분석한 결과를 다룬다. 따라서 국내 원자력시설의 우라늄 농축도 검증을 위한 IAEA 안전조치 사찰 결과를 분석한 논문이 별로 발표되지 않은 상황에서, 본 논문은 안전조치 검사 결과 분석에도 유익할 것으로 판단된다. 개발된 방사선 검출기의 개선 사항도 함께 논의하였으므로 향후 관련 분야 방사선 검출기 개발에도 기여할 것으로 예상된다.

• 핵의학기술
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• 제21권2호
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• pp.80-85
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• 2017

D530c는 cadmium zinc telluride (CZT) detector가 심장을 중심으로 배열되어 회전 없이 짧은 시간에 검사가 가능하며 높은 해상도의 영상획득이 가능하다. 하지만 이러한 구조적 특성으로 인해 환자의 움직임에 민감하며, 검사 결과에도 일부분 영향을 미칠 수 있다. 이에 본 연구에서는 D530c에서 검사 중 발생되는 환자의 움직임 감소 활동을 통해 영상 품질의 최적화를 목적으로 한다. 환자의 다양한 움직임 원인을 분석하여 호흡보정 도구 제작, 환자의 호흡 및 움직임에 관한 주의사항 교육 등의 개선활동을 시행하였다. 개선 전 대상으로 2016년 11월에 D530c에서 심근관류 SPECT를 시행한 환자 70명을 선정하였고, 개선 후 2017년 2월 14일부터 2017년 2월 21일까지 시행한 환자 70명을 대상으로 하였다. 검사 시작 전 위치에서 X, Y, Z 축으로 이동된 심장의 변동거리(4 mm, 8 mm, 12 mm 이상)별 움직임 발생시간을 측정하여 개선 전 후 Stress와 Rest 영상을 각각 비교 분석하였다. 개선활동 후 심장의 움직임 발생시간이 stress와 rest 영상에서 모두 감소되었으며, 특히 stress 영상에서 12 mm 이상의 큰 움직임 발생횟수가 0회(발생시간 0초)로 기록되었다. 심장의 위치가 X축으로 4 mm, 8 mm 변동된 발생시간과 Z축으로 8 mm 변동된 발생시간은 통계적으로 유의한 차이가 있었지만(p<0.005), 그 외 stress와 rest의 모든 구간의 발생시간은 유의한 차이가 없었다(p>0.005). 호흡에 의해서도 발생 가능한 4 mm 변동거리에 따른 움직임 발생시간의 감소는 교육 및 움직임 방지 도구를 통해 검사 중 환자의 호흡이 보정된 결과로 파악되며, 호흡 이외의 환자의 실제 움직임으로 발생되었을 것으로 예상되는 8 mm, 12 mm 이상의 변동거리에 따른 움직임 발생시간 감소를 통해 영상 품질의 향상을 가져올 것으로 예상된다.