• 제목/요약/키워드: HPGe

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Performance of a Compton Suppression Spectrometer of the SNU-KAERI PGAA Facility

  • Sun Gwang Min;Park Chang Su;Choi H.D.
    • Nuclear Engineering and Technology
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    • v.35 no.4
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    • pp.347-355
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    • 2003
  • The \gamma-ray spectrometer of the PGAA (Prompt Gamma Activation Analysis) facility constructed at HANARO of the Korea Atomic Energy Research Institute was upgraded to the multi-mode spectrometer including the single mode, the Compton suppression mode and the pair mode. The performance of the spectrometer was tested and summarized. The background count rate and the uncertainty of the detection efficiency were reduced greatly in comparison with those before the new installation.

Measurement of Gamma ray Spectrum for the 27Al(p,3p+n)24Na Nuclear Reaction by using 100 MeV Proton Acceleration System (100 MeV 양성자가속기를 이용한 27Al(p,3p+n)24Na 핵반응에 대한 감마선 스펙트럼 측정)

  • Lee, Samyol
    • Journal of the Korean Society of Radiology
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    • v.9 no.1
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    • pp.55-59
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    • 2015
  • Research about the proton nuclear reaction is actively achieving on the proton therapy including material development of fusion reactor. The proton induced gamma ray energy(2754, 1386 keV) spectrum of 27Al(p,3p+n)24Na reaction was measured with 100 MeV high energy proton beam. The proton beam in the experiment was derived from 100 MeV proton linear accelerator in the KOMAC. We measured the gamma ray intensity ratio of the decay level from the energy spectrum. The previous results have been compared with the current result. Strength of measured gamma rays will provide very important information though decide high energy gamma radiation detection efficiency.

A Study on Minimum Detection Limit of Environmental Radioactivity in HPGe Detector (HPGe 검출기에서 환경방사능측정의 검출하한치에 관한 연구)

  • Jang, Eun-Sung
    • Journal of the Korean Society of Radiology
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    • v.5 no.1
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    • pp.5-10
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    • 2011
  • Based on basic concept of detection limit, sample measurement time & background measurement time was considered, and MDA values according to background measurement time and sample measurement time in land samples(river soil, surface soil, drinking water, underground water, surface water, pine leaf, mugwort) analysis among environmental samples were compared. Seeing the water sample analysis result, it was shown that most of the samples were not detected, and most of the samples in land specimen analysis showed to be below the detection limit of "Ministry of Education, Science and Technology Announcement Je-2008-28-ho", but $^{137}Cs$ which is one of artificial radioactive nuclide was detected in some samples. It can be traced back to 1950s and 1960s when nuclear tests were carried out in atmosphere and catastrophic Chernobyl atomic power station accident that caused fallouts in the sky, and this is common level of detection that can be observed worldwide. Seeing the result that the $^{134}Cs$(which is a isotope of $^{137}Cs$, and it has relatively short half life) was not detected in all samples, it can be considered it doesn't affect to the operation of atomic power station.

A Study on Measurement of Gamma-ray Spectrum for the Natural Tungsten nuclear reaction by using KOMAC proton Linear Accelerator (KOMAC 양성자 선형가속기를 이용한 천연 텅스텐 핵반응에 대한 감마선 스펙트럼 측정에 대한 연구)

  • Lee, Samyol
    • Journal of the Korean Society of Radiology
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    • v.12 no.2
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    • pp.133-138
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    • 2018
  • The measurement of gamma-ray spectrum of $^{nat}W(p,xn)$ reaction with natural tungsten were performed by using a high energy proton generated from a 100-MeV proton linear accelerator of the Korea Multi-purpose Accelerator Complex (KOMAC). Gamma rays generated by various nuclides generated through the nuclide were measured using a gamma-ray spectroscopy system composed of HPGe detector. A gamma-ray standard source was used for energy calibration and efficiency measurement of the detector. Analysis of the gamma rays observed in the measured spectra showed that the radionuclides produced were $^{167}Re$, $^{178}Re$, $^{179}Re$, $^{180}Re$, $^{181}Re$, $^{182}Re$, $^{184}Re$, $^{172}Ta$, $^{174}Ta$, $^{178}Ta$, $^{182}Ta$, $^{184}Ta$, $^{175}W$, $^{176}W$, $^{177}W$ and $^{179}W$. Nuclides were generated. The results of this study will be applied to nuclear fusion, astrophysics, and nuclear medicine applications in the future.

Elemental Analysis of Bottom Ash from Incinerator by Neutron Activation Analysis (중성자 방사화분석법을 이용한 소각로 바닥재의 원소분석)

  • Moon, Jong-Hwa;Kang, Sang-Hoon;Kim, Sun-Ha;Chung, Young-Sam
    • Analytical Science and Technology
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    • v.16 no.5
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    • pp.418-425
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    • 2003
  • Inorganic elemental content of bottom ash generated from municipal solid waste incinerator was determined by neutron activation analysis. Bottom ash samples were collected monthly from incinerator located in city D, strained out by the 5 mm sieve, dried by oven and pulverized by agate mortar. The samples were irradiated at NAA #1 irradiation hole in HANARO research reactor of Korea Atomic Energy Research Institute and the irradiated samples were measured by HPGe-gamma-ray spectrometer. From the activity of measured nuclides, 33 elements including As, Cr, Cu, Fe, Mn, Sb and Zn were determined applying activity creation formula and nuclear data. The quality control was conducted by simultaneous analysis with NIST standard reference materials.

Nuclide Identification of Gamma Ray Energy Peaks from an Air Sample for the Emergency Radiation Monitoring (비상시 환경방사능 모니터링을 위한 공기부유진 시료의 감마선에너지 스펙트럼에 대한 핵종판별)

  • Byun, Jong-In;Yoon, Seok-Won;Choi, Hee-Yeoul;Yim, Seong-A;Lee, Dong-Myung;Yun, Ju-Yong
    • Journal of Radiation Protection and Research
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    • v.34 no.4
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    • pp.170-175
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    • 2009
  • For the emergency radiation monitoring using gamma spectrometry, we should sufficiently survey the background spectra as environmental samples with systematic nuclide identification method. In this study, we obtained the gamma ray energy spectrum using a HPGe gamma spectrometry system from an air sample. And we identified nuclide of the gamma ray energy peaks in the spectrum using two methods -1) Half life calculation and 2) survey for cascade coincidence summing peaks using nuclear data. As the results, we produced the nuclide identification results for the air sample.

Measurement of 137Cs in Ice Core Samples from Antarctica

  • Lim, S.I.;Kim, D.H.;Huh, J.Y.;Lee, J.;Hahn, I.S.;Han, Y.C.;Hur, S.D.;Hwang, H.J.;Kang, W.G.;Kim, Y.D.;Lee, E.K.;Lee, M.H.
    • Journal of the Korean Physical Society
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    • v.73 no.9
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    • pp.1263-1268
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    • 2018
  • Three different ice core samples from Antarctica were analyzed to identify activity concentrations of radioactive isotopes. Tracking migration of radioactive isotopes to Antarctica can provide a key clue to understand global environmental changes caused by radiation exposures because the Antarctic ice cores can preserve unique characteristics of various environmental conditions. We are particularly interested in the $^{137}Cs$ nucleus, because it is closely related to radiation exposure from nuclear power plant accidents and nuclear bomb tests. With its half life of $30.17{\pm}0.03$ years, $^{137}Cs$ can also be used to assess the age of sedimentation occurring after around the year 1945. We selected three ice core samples, called Tarn8, Styx27, and H25, from different time periods; the Tarn8 sample is known to be from earlier than ~ 1000 AD, the Styx27 sample is approximately from the year 1945, and the H25 sample is from the year 2012. Radioactive isotope measurements of the ice core samples were performed using a 100% HPGe detector at Cheongpyeong Underground Radiation Laboratory (CURL). We measured the activity of $^{137}Cs$ in the H25 sample to be $0.98{\pm}0.82mBq/kg$. Although the activity has a large uncertainty mainly due to the limited sample quantity, the $^{137}Cs$ isotopes in the Antarctic ice core were measured for the first time in Korea.

Efficiency calibration of a coaxial HPGe detector-Marinelli beaker geometry using an 152Eu source prepared in epoxy matrix and its validation by efficiency transfer method

  • Yucel, Haluk;Zumrut, Senem;Nartturk, Recep Bora;Gedik, Gizem
    • Nuclear Engineering and Technology
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    • v.51 no.2
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    • pp.526-532
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    • 2019
  • In this study, an in-house $^{152}Eu$ calibration source was produced from a custom epoxy matrix with a density of ${\rho}=1.14g\;cm^{-3}$, which is chemically stable and durable form after its solidification. The homogeneity of $^{152}Eu$ in matrix was obtained better than 98%. For a Marinelli beaker geometry, an efficiency calibration procedure was applied to a n-type, coaxial, 78.5% relative efficient HPGe detector in the energy range of 121.7-1408.0 keV by using in-house $^{152}Eu$ calibration source. Then the measured efficiencies for Marinelli geometry were compared with the results calculated by MEFFTRAN and ANGLE softwares for the validation. Although MEFFTRAN and ANGLE have two different efficiency transfer algorithms to calculate the efficiencies, they usually need to use a reliable and accurate reference efficiency values as input data. Hence, reference efficiency values were obtained experimentally from a multinuclide standard source for the same detector-Marinelli geometry. In the present source characterization, the corrections required for self-absorption and true coincidence summing effects for $^{152}Eu$ gamma-rays were also obtained for a such close counting geometry condition. The experimental results confirmed the validity of efficiency calculations obtained by MEFFTRAN and ANGLE softwares that are calculation tools.

Source and LVis based coincidence summing correction in HPGe gamma-ray spectrometry

  • Lee, Jieun;Kim, HyoJin;Kye, Yong Uk;Lee, Dong Yeon;Kim, Jeung Kee;Jo, Wol Soon;Kang, Yeong-Rok
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1754-1759
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    • 2022
  • The activity of gamma-ray emitting nuclides is calculated assuming that each gamma-ray is detected individually; thus, the magnitude of the coincidence summing signal must be considered during activity calculations. Here, the correction factor for the coincidence summing effect was calculated, and the detection efficiencies of two HPGe detectors were compared. The CANBERRA Inc. GC4018 high-purity Ge detector provided an estimate for the peak-to-total ratio using a point source to determine the coincidence summing correction factor. The ORTEC Inc. GEM60 high-purity Ge detector uses EFFTRAN in LVis to obtain the parameters of the detector and source model and the gamma-gamma and gamma-X match estimates, in order to determine the coincidence summing correction factor. Nuclide analyses, radioactivity comparisons, and analyses of reference material samples were performed utilizing certified reference materials to accurately determine the detection efficiencies. For both Co-60 and Y-88, the detection efficiency for a point source increased by an average of at least 12-13%, whereas the detection efficiency determined using LVis increased by an average of at least 13-15%. The calculated radioactivity values of the certified reference material and reference material samples were accurate to within 3% and 6% of the measured values, respectively.

Assessment of radionuclides from coal-fired brick kilns on the outskirts of Dhaka city and the consequent hazards on human health and the environment

  • M.M. Mahfuz Siraz;M.D.A. Rakib;M.S. Alam;Jubair Al Mahmud;Md Bazlar Rashid;Mayeen Uddin Khandaker;Md. Shafiqul Islam;S. Yeasmin
    • Nuclear Engineering and Technology
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    • v.55 no.8
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    • pp.2802-2811
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    • 2023
  • In a first-of-its-kind study, terrestrial radionuclide concentrations were measured in 35 topsoil samples from the outskirts of Dhaka using HPGe gamma-ray spectrometry to assess the radiological consequences of such a vast number of brick kilns on the plant workers, general as well as dwelling environment. The range of activity concentrations of 226Ra, 232Th, and 40K is found at 19 ± 3.04 to 38 ± 4.94, 39 ± 5.85 to 57 ± 7.41, and (430 ± 51.60 to 570 ± 68.40) Bq/kg, respectively. 232Th and 40K concentrations were higher than the global averages. Bottom ash deposition in lowlands, fly ash buildup in soils, and the fallout of micro-particles are all probable causes of the elevated radioactivity levels. 137Cs was found in the sample, which indicates the migration of 137Cs from nuclear accidents or nuclear fallout, or the contamination of feed coal. Although the effective dose received by the general public was below the recommended dose limit but, most estimates of hazard parameters surpass their respective population weighted global averages, indicating that brick kiln workers and nearby residents are not safe due to prolonged exposures to terrestrial radiation. In addition, the soil around sampling sites is found to be unsuitable for agricultural purposes.