• Journal of Radiation Protection and Research
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• 제38권2호
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• pp.119-123
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• 2013

HPGe 검출기를 사용하는 감마 분광분석계의 건전성을 점검하기 위한 실험실 선원이 개발되었다. 점검 선원은 0.154 mm 이하의 라듐이 풍부한 토양을 밀봉된 원통형 시료 용기에 담은 것으로, 검출기 교정에 사용할 12 개의 감마선이 방출된다. 점검 선원의 스펙트럼은 1년 동안 1개월 간격으로 측정하였으며, 스펙트럼에 나타난 감마선 피크들의 특성을 조사하였다. 감마 분광분석계가 정상일 때 라듐과 그 붕괴 생성물에서 3% 이상 방출률을 갖는 감마선들의 피크면적과 반치폭은 77 keV 피크를 제외하고는 각각 표준편차 2%와 3% 이내에서 일정하였다. 따라서 점검 선원은 77 keV부터 2202 keV까지 영역에 있는 10개의 피크를 사용하여 분광분석계의 건전성을 점검하는데 충분한 것으로 판단되었다.

• 대한방사선방어학회:학술대회논문집
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• 대한방사선방어학회 2009년도 춘계 학술발표
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• pp.128-129
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• 2009

• Journal of Radiation Protection and Research
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• 제35권3호
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• pp.105-110
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• 2010

고순도 반도체 감마분광시스템을 이용하여 토양 시료를 파괴하지 않고 화학 전처리 단계가 필요없는 우라늄 방사능 분석 기술을 개발하였다. 본 논문에서 제시한 방법을 이용한 분석결과와 기존에 일반적으로 사용하는 알파분광분석법(Alpha Spectrometry)의 결과를 비교하였다. 비교결과 불확도 범위 내에서 비슷한 측정값을 보였다. 따라서 본 논문에서 제시한 방법은 토양시료의 우라늄 분석에 이용될 수 있을 것이다.

• 대한방사선방어학회:학술대회논문집
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• 대한방사선방어학회 2009년도 춘계 학술발표
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• pp.250-251
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• 2009

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.533-534
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• 2018

• 방사성폐기물학회지
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• 제12권2호
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• pp.97-105
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• 2014

HPGe 감마선 검출기를 이용하여 $^{226}Ra$의 방사능을 직접 측정방법의 경우, $^{226}Ra$의 186.21 keV 감마선이 $^{235}U$에서 방출되는 185.7 keV 감마선에 의한 간섭을 받기 때문에 피크면적의 계산에서 반드시 보정이 필요하다. 비록 분해능이 아주 우수한 HPGe 검출기를 사용한다 하더라도 그리고 분광시스템의 채널수를 최대로 늘린다고 할지라도 약 0.5 keV 차이의 두 감마선 피크를 분리해 내기란 현실적으로 어려운 일이다. 본 연구에서는 감마분광분석을 이용한 $^{226}Ra$의 직접 측정방법에 대한 적용성을 평가하기 위하여, 여러 가지 간섭피크 보정들을 이용한 직접 측정방법을 조사하였다. 이를 원료물질 및 공정부산물 시료들에 적용함으로써 직접 측정방법들에서 그 측정 불확도, 직선성 및 적용범위 등을 평가하였다. 최종적으로 방사평형 관계를 이용하여 $^{226}Ra$의 방사능을 측정하는 간접 측정방법으로부터 얻은 $^{214}Pb$ 및 $^{214}Bi$의 결과를 직접 측정방법의 결과와 비교함으로써 최적의 측정방법을 유도하였다.

• Nuclear Engineering and Technology
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• 제55권1호
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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.

• Journal of Radiation Protection and Research
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• 제46권3호
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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.

• Journal of Radiation Protection and Research
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• 제34권4호
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• pp.170-175
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• 2009

감마선분광분석법을 이용하여 비상시 환경방사능 모니터링을 수행할 경우 스펙트럼 측정시 해당 시료의 종류에 따른 백그라운드 자료 확보와 이를 활용한 체계적인 핵종확인 과정이 선행되어야 한다. 비상시 환경방사능 모니터링을 고려하여 24시간 동안 포집 후 회화시킨 공기부유진 시료를 HPGe 감마선분광분석 시스템으로 계측하여 감마선에너지 스펙트럼을 얻었으며, 그 스펙트럼에서 보이는 피이크들의 핵종을 판별하기 위해 두 가지 방법 - 1) 반감기 추정 2) 핵자료를 이용한 축차우연동시합성피이크 확인 - 으로 접근하였다. 그 결과로서 공기부유진의 감마선에너지스펙트럼에 대한 핵종판별결과 자료를 산출하였다.

• Nuclear Engineering and Technology
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• 제44권7호
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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.