• Title/Summary/Keyword: HPGe Gamma Spectrometry

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Development of a simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector (HPGe 검출기를 사용한 감마분광분석계의 점검선원 개발)

  • Lee, Mo Sung
    • Journal of Radiation Protection and Research
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    • v.38 no.2
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    • pp.119-123
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    • 2013
  • A simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector was developed. The check source consists of radium-riched soil which was ground in size of less than 0.154mm and contained in air tight cylinderical vial, and provides photons with 12 distinct energies. The spectra of the check source were measured once a month during one year, analyzed the charactreictics of their peaks. When the gamma spectrometry system was in normal state, the areas and FWHMs of the gamma rays with more than 3% gamma emission rate in radium and its decay products was constant within standard deviation 2% and 3%, respectively, except 77 keV peak. And it was found that this check source can play a sufficient role to check the integrity of a gamma spectrometry system using 10 peaks in the range of 77 to 2202 keV.

Uranium Activity Analysis of Soil Sample Using HPGe Gamma Spectrometer (고순도 반도체(HPGe) 감마분광시스템을 이용한 토양 중 우라늄 방사능 분석)

  • Lee, Wan-No;Kim, Hee-Reyoung;Chung, Kun-Ho;Cho, Young-Hyun;Kang, Mun-Ja;Lee, Chang-Woo;Choi, Geun-Sik
    • Journal of Radiation Protection and Research
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    • v.35 no.3
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    • pp.105-110
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    • 2010
  • Using N-type HPGe gamma spectrometer, uranium analysis technique of soil sample is developed where the chemical preprocessing is not a necessity. The results of uranium activities using the method presented in this paper were compared with those results with conventional alpha spectrometer and two results were similar from within uncertainty range. Therefore, this new method will be applied in uranium activity analysis of soil sample.

Feasibility about the Direct Measurement of 226Ra Using the Gamma-Ray Spectrometry (감마분광분석을 이용한 226Ra의 직접 측정방법에 대한 적용성 평가)

  • Ji, Young-Yong;Chung, Kun Ho;Lim, Jong-Myoung;Kim, Change-Jong;Jang, Mee;Kang, Mun Ja;Park, Sang Tae;Woo, Zuhee;Koo, Boncheol;Seo, Bokyun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.2
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    • pp.97-105
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    • 2014
  • In the case of the direct measurement of $^{226}Ra$ using a HPGe gamma-ray spectrometer, the interference between gammarays with 186.21 keV of $^{226}Ra$ and 185.7 keV of $^{235}U$ should be corrected to calculate the net peak area in the energy spectrum. In general, it is very difficult to conduct peaks stripping with difference of about 0.5 keV, although a HPGe with the superior resolution is applied and the maximum channels is applied to the spectrometer. In this study, several interference correction techniques in the direct measurement were surveyed to evaluate the feasibility for the measurement of $^{226}Ra$ using the gamma-ray spectrometery. Applying the interference corrections to the analysis of raw materials and by-products, the method validation for the direct measurement of $^{226}Ra$ was conducted by evaluating the measurement uncertainty, linearity, and range. As a result, the optimum method of the interference correction was selected by comparing with the indirect measurement of which progenies of $^{226}Ra$, such as $^{214}Pb$ and $^{214}Bi$, were analyzed in the secular equilibrium state.

Database of virtual spectrum of artificial radionuclides for education and training in in-situ gamma spectrometry

  • Yoomi Choi;Young-Yong Ji;Sungyeop Joung
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.190-200
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    • 2023
  • As the field of application of in-situ gamma spectroscopy is diversified, proficiency is required for consistent and accurate analysis. In this study, a program was developed to virtually create gamma energy spectra of artificial nuclides, which are difficult to obtain through actual measurements, for training. The virtual spectrum was created by synthesizing the spectra of the background radiation obtained through actual measurement and the theoretical spectra of the artificial radionuclides obtained by a Monte Carlo simulation. Since the theoretical spectrum can only be obtained for a given geometrical structure, representative major geometries for in-situ measurement (ground surface, concrete wall, radioactive waste drum) and the detectors (HPGe, NaI(Tl), LaBr3(Ce)) were predetermined. Generated virtual spectra were verified in terms of validity and harmonization by gamma spectrometry and energy calibration. As a result, it was confirmed that the energy calibration results including the peaks of the measured spectrum and the peaks of the theoretical spectrum showed differences of less than 1 keV from the actual energies, and that the calculated radioactivity showed a difference within 20% from the actual inputted radioactivity. The verified data were assembled into a database and a program that can generate a virtual spectrum of desired condition was developed.

Determination of 226Ra in TENORM Sample Considering Radon Leakage Correction

  • Lim, Sooyeon;Syam, Nur Syamsi;Maeng, Seongjin;Lee, Sang Hoon
    • Journal of Radiation Protection and Research
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    • v.46 no.3
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    • pp.127-133
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    • 2021
  • Background: Phosphogypsum is material produced as a byproduct in fertilizer industry and is generally used for building materials. This material may contain enhanced radium-226 (226Ra) activity concentration compared to its natural concentration that may lead to indoor radon accumulation. Therefore, an accurate measurement method is proposed in this study to determine 226Ra activity concentration in phosphogypsum sample, considering the potential radon leakage from the sample container. Materials and Methods: The International Atomic Energy Agency (IAEA) phosphogypsum reference material was used as a sample in this study. High-purity germanium (HPGe) gamma spectrometry was used to measure the activity concentration of the 226Ra decay products, i.e., 214Bi and 214Pb. Marinelli beakers sealed with three different sealing methods were used as sample containers. Due to the potential leakage of radon from the Marinelli beaker (MB), correction to the activity concentration resulted in gamma spectrometry is needed. Therefore, the leaked fraction of radon escaped from the sample container was calculated and added to the gamma spectrometry measured values. Results and Discussion: Total activity concentration of 226Ra was determined by summing up the activity concentration from gamma spectrometry measurement and calculated concentration from radon leakage correction method. The results obtained from 214Bi peak were 723.4 ± 4.0 Bq·kg-1 in MB1 and 719.2 ± 3.5 Bq·kg-1 in MB2 that showed about 5% discrepancy compared to the certified activity. Besides, results obtained from 214Pb peak were 741.9 ± 3.6 Bq·kg-1 in MB1 and 740.1 ± 3.4 Bq·kg-1 in MB2 that showed about 2% difference compared to the certified activity measurement of 226Ra concentration activity. Conclusion: The results show that radon leakage correction was calculated with insignificant discrepancy to the certified values and provided improvement to the gamma spectrometry. Therefore, measuring 226Ra activity concentration in TENORM (technologically enhanced naturally occurring radioactive material) sample using radon leakage correction can be concluded as a convenient and accurate method that can be easily conducted with simple calculation.

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.

NEW DEVELOPMENT OF HYPERGAM AND ITS TEST OF PERFORMANCE FOR γ-RAY SPECTRUM ANALYSIS

  • Park, B.G.;Choi, H.D.;Park, C.S.
    • Nuclear Engineering and Technology
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    • v.44 no.7
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    • pp.781-790
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    • 2012
  • The HyperGam program was developed for the analysis of complex HPGe ${\gamma}$-ray spectra. The previous version of HyperGam was mainly limited to the analysis of ${\gamma}$-ray peaks and the manual logging of the result. In this study, it is specifically developed into a tool for the isotopic analysis of spectra. The newly developed features include nuclide identification and activity determination. An algorithm for nuclide identification was developed to identify the peaks in the spectrum by considering the yield, efficiency, energy and peak area for the ${\gamma}$-ray lines emitted from the radionuclide. The detailed performance of nuclide identification and activity determination was accessed using the IAEA 2002 set of test spectra. By analyzing the test spectra, the numbers of radionuclides identified truly (true hit), falsely (false hit) or missed (misses) were counted and compared with the results from the IAEA 2002 tests. The determined activities of the radionuclides were also compared for four test spectra of several samples. The result of the performance test is promising in comparison with those of the well-known software packages for ${\gamma}$-ray spectrum analysis.