• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1259-1265
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• 2020

A beta ray scanner was proposed for in-situ discrimination of beta and gamma ray radioactivity. This scanner is based on the principle that gamma and beta rays experience different changes in detection efficiency in scintillators with different geometries, especially with regard to the scintillator thickness. The ratios of the counting rates of gamma rays (R_gamma), beta rays (R_beta), and sample measurements (R_total) in a thick scintillator to those in a thin one are reported. The parameter X_thick, which represents the counting rate contributed by beta rays to the total counting rate in the thick scintillator, was derived as a function of those ratios. The values of R_gamma and R_beta for ⁶⁰Co and ⁹⁰Sr sources were estimated as 3.2 ± 0.057 and 0.99 ± 0.0049, respectively. The estimated beta ray contributions had relative standard deviations of 2.05-4.96%. The estimated range of the beta rays emitted from ⁹⁰Sr was 19 mm as per the Monte Carlo N-Particle simulation, and this value was experimentally verified. Homogeneous and surface contaminations of ⁶⁰Co and ⁹⁰Sr-⁹⁰Y were simulated for application of the proposed method. The counting rate contributed by the beta rays was derived and found to be proportional to the concentration of ⁹⁰Sr-⁹⁰Y contamination.

• Nuclear Engineering and Technology
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• 제30권5호
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• pp.452-461
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• 1998

The pin power distribution is determined by analyzing the rotational gamma scanning data for 36 element fuel bundle of HANARO. A fission monitor of Nb$^{95}$ is chosen by considering the criteria of the half-life, fission yield, emitting ${\gamma}$-ray energy and probability. The ${\gamma}$-ray spectra were measured in Korea Atomic Energy Research Institute(KAERI) by using a HPGe detector and by rotating the fuel bundle at steps of 10$^{\circ}$. The counting rates of Nb$^{95}$ 766 keV ${\gamma}$-rays are determined by analyzing the full absorption peak in the spectra. A 36$\times$36 response matrix is obtained from calculating the contribution of each rod at every scanning angle by assuming 2-dimensional and parallel beam approximations for the measuring geometry. In terms of the measured counting rates and the calculated response matrix, an inverse problem is set up for the unknown distribution of activity concentrations of pins. To select a suitable solving method, the performances of three direct methods and the iterative least-square method are tested by solving simulation examples. The final solution is obtained by using the iterative least-square method that shows a good stability. The influences of detection error, step size of rotation and the collimator width are discussed on the accuracy of the numerical solution. Hence an improvement in the accuracy of the solution is proposed by reducing the collimator width of the scanning arrangement.

• 대한방사선기술학회지:방사선기술과학
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• 제39권4호
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• pp.557-564
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• 2016

요오드 조영제 사용 및 밀도에 따라 감마카메라 영상의 감마선 계수율에 미치는 영향과 SPECT/CT 감쇠보정에서 CT 흡수계수를 이용한 감쇠 보정 시 조영제 유/무에 따라 계수율의 변화에 대하여 알아보고자 한다. 실험 재료는 $^{99m}TcO_4$ 370 MBq와 요오드 조영제인 Pamiray 370 mg, Iomeron 350 mg, Visipaque 320 mg, Bonorex 300 mg를 사용하였다. 영상획득은 $^{99m}TcO_4$ 투여 후 30분에 평면영상을 각각 1분, 2분, 3분, 4분, 5분 동안 촬영 하였고, 단층영상은 55분에 20분 동안 frame 당 20 sec으로 60 view를 촬영하였다. 평면영상에서 $^{99m}TcO_4$와 생리식염수를 혼합 했을 때 보다 요오드 조영제 밀도의 종류에 따라 혼합한 경우 촬영시간에 따른 감마선 계수율이 감소되어 통계적 유의한 차이가 있었다. $^{99m}TcO_4$와 생리식염수를 혼합한 단층영상에서 CT 흡수계수로 보정 전/후 감마선 계수율은 평균 $182{\pm}26counts$, $531.3{\pm}34counts$ 이다. $^{99m}TcO_4$와 생리식염수에 요오드 조영제를 혼합한 단층영상에서요오드 조영제의 밀도에 따라 CT 흡수계수로 감쇠보정 전 평균 $166{\pm}29$, $158.3{\pm}17$, $154{\pm}36$, $150{\pm}33counts$ 이었고, 감쇠보정 후 평균 $515{\pm}30$, $503{\pm}10$, $496{\pm}31$, $488.7{\pm}33counts$으로 요오드 조영제를 혼합하지 않은 영상과 비교 평가 시 모두 유의한 차이가 있었다. 따라서 요오드 조영제의 사용에 따른 감마카메라 영상에서 감마선 계수율에 영향을 주기 때문에 진료 당일 여러 종류의 검사를 시행하기 전 반드시 선행되어야 할 검사를 선별하여 타 검사로 인해 잘못된 결과를 얻지 않아야 한다.

• Journal of Radiation Protection and Research
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• 제43권3호
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• pp.85-96
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• 2018

Background: A variety of inorganic scintillators have been developed and improved for use in radiation detection and measurement, and in situ gamma-ray spectrometry in the environment remains an important area in nuclear safety. In order to verify the feasibility of promising scintillators in an actual environment, a performance test is necessary to identify gamma-ray peaks and calculate the radioactivity from their net count rates in peaks. Materials and Methods: Among commercially available scintillators, $LaBr_3(Ce)$ scintillators have so far shown the highest energy resolution when detecting and identifying gamma-rays. However, the intrinsic background of this scintillator type affects efficient application to the environment with a relatively low count rate. An algorithm to subtract the intrinsic background was consequently developed, and the in situ calibration factor at 1 m above ground level was calculated from Monte Carlo simulation in order to determine the radioactivity from the measured net count rate. Results and Discussion: The radioactivity of six natural radionuclides in the environment was evaluated from in situ gamma-ray spectrometry using an $LaBr_3(Ce)$ detector. The results were then compared with those of a portable high purity Ge (HPGe) detector with in situ object counting system (ISOCS) software at the same sites. In addition, the radioactive cesium in the ground of Jeju Island, South Korea, was determined with the same assumption of the source distribution between measurements using two detectors. Conclusion: Good agreement between both detectors was achieved in the in situ gamma-ray spectrometry of natural as well as artificial radionuclides in the ground. This means that an $LaBr_3(Ce)$ detector can produce reliable and stable results of radioactivity in the ground from the measured energy spectrum of incident gamma-rays at 1 m above the ground.

• 한국방사선학회논문지
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• 제2권1호
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• pp.31-34
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• 2008

The neutron capture spectrum for the light nuclide was very useful to study the nuclear structure. In the present study, the capture gamma-ray from the 27-keV resonance of $^{19}F(n,g)^{20}F$ reaction were measured with an anti-Compton NaI(Tl) spectrometer and the 3-MV Pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo institute of technology. A neutron Time-of-Flight method was adopted with a 1.5 ns pulsed neutron source by the $^7Li(p,n)^7Be$ reaction. In the present experiment, a Teflon(($CF_2$)n) sample was used The sample was disk with a diameter of 90mm. The thickness of sample was determined so that reasonable counting rates could be obtained and the correction was not so large for the self-shielding and multiple scattering of neutrons in the sample, and was 5mm. The primary gamma-ray transitions were compared with previous measurement of Kenny.

• 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.

• 한국의학물리학회지:의학물리
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• 제13권4호
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• pp.229-233
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• 2002

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.