• Nuclear Engineering and Technology
• /
• 제51권2호
• /
• pp.526-532
• /
• 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.

• 분석과학
• /
• 제13권6호
• /
• pp.743-750
• /
• 2000

라듐 및 라돈과 같은 환경 방사성 핵종의 분석 방법 중 HPGe 검출기를 이용한 감마선 분광 분석법은 대부분 플라스틱 용기를 많이 이용하고 있다. 그러나 플라스틱 용기는 대기 중 라돈 딸 핵종의 흡착에 의해 백그라운드가 증가할 뿐만 아니라 방사 평형 과정에서 생성된 기체 상의 라돈의 손실에 의하여 완전한 방사 평형에 도달하지 않는다는 것이다. 이러한 문제점을 해결하기 위하여 알루미늄 재질의 측정 용기를 제작하였고, 그 특성을 조사하였다. 알루미늄 용기를 이용하여 방사 평형 과정을 조사한 결과, 고체 및 액체 시료 모두 기체 상태의 라돈 손실 없이 라듐과 그 딸핵종들이 측정 용기 안에서 완전한 방사 평형에 도달하는 것을 알았다. 또한 감마선 분광 분석법을 이용한 고체 및 액체 시료 중의 라듐 및 라돈의 비파괴 분석이 가능함을 확인하였다.

• 분석과학
• /
• 제28권3호
• /
• pp.228-235
• /
• 2015

본 연구는 지하수 중 라듐(²²⁶Ra) 분석을 위해 고상추출디스크(solid phase extraction disk)를 이용한 감마선분광분석법(이하 고상추출디스크법)을 제안하고 액체섬광계수기를 이용한 액체섬광계수(liquid scintillation counter, LSC)법 및 마리넬리비커(Marinelli beaker)를 이용한 감마선분광분석기(gamma ray spectrometer)법(이하 마리넬리비커법)과의 회수율 비교를 통해 적용성을 검토하였다. ²²⁶Ra을 회수한 고상추출디스크는 딸핵종의 방출을 방지하기 위해 폴리에틸렌 필름으로 밀봉 후 감마선분광분석기로 분석하였다. 24일 경과 후, ²²⁶Ra과 딸핵종인 ²¹⁴Bi과 ²¹⁴Pb이 방사평형 된 것으로 확인되었다. 라듐 표준물질을 이용하여 고상추출디스크법으로 분석한 딸핵종 ²¹⁴Bi와 ²¹⁴Pb의 회수율은 각각 80% (295.21 Kev)와 104% (351.92 Kev)로 액체섬광계수법보다 높게 나타났다. 바탕시료(blank) 측정시 감마선분광분석기 챔버내 질소를 주입했을 경우는 주입하지 않았을 경우보다 간섭치가 약 10% 이하로 낮아지는 것을 확인하였으며, 5 L 시료를 8만초 동안 측정한 검출한계는 0.17~0.40 pCi/L로 분석되어 미국 EPA 기준치인 1pCi/L를 만족하였다. 고상추출디스크법과 액체섬광계수법을 이용한 7개 지하수 시료 분석 결과, 두 방법의 상관계수(correlation coefficient)는 0.987로 나타나 추가적인 분석을 통해 통계적 유의성을 확보한다면 고상추출디스크법의 적용가능성이 높을 것으로 판단된다. 결과적으로, 고상추출디스크법을 이용한 지하수 중 ²²⁶Ra 농도 분석은 전처리 과정이 비교적 단순하여 분석시간이 절약되고 높은 회수율과 낮은 검출한계치 등의 장점을 가지고 있는 것으로 분석되었다. 또한 고상추출디스크법은 액체섬광계수법과 마리넬리비커법에 비해 많은 양의 시료를 전처리하기 쉽기 때문에 저준위 시료 분석에 유용할 것으로 판단된다.

• Journal of Radiation Protection and Research
• /
• 제31권1호
• /
• pp.47-52
• /
• 2006

$0.3g/cm^3$ 에서 $1.5g/cm^3$까지 다양한 겉보기 밀도를 갖는 감마방출핵종 환경시료의 정확한 방사능 분석을 위해서 자체흡수보정(self-absorption correction)은 중요한 문제이다. 방사선 표준선원을 밀도별로 제작할 필요없이 마리넬리 비커를 감싸는 외부용기를 새롭게 제작하여 실용적이면서 간단한 자체흡수보정방법을 본 논문에서 제시하였다. 밀도 0.8, 1.0, $1.3g/cm^3$ 대해서 새로운 방법을 이용하여 자체흡수보정을 한 효율들과 밀도별로 직접 표준선원용액을 만들어 측정한 효율값이 4 % 이내에서 일치하였다.

• Journal of Radiation Protection and Research
• /
• 제11권1호
• /
• pp.70-76
• /
• 1986

중성자 측정의 국가표준을 확립하기 위하여 국제원자력거주(IAEA)로 부터 기술지원을 받아서 $MnSO_4$용액조장치를 개발하였다. 본 용액조장치는 구형의 s.s. 316L $MnSO_4$용액조(두께 3.5mm, 내경 125cm), 용액의 순환계 및 5$^{56}Mn\;{\gamma}$-선 검출계동으로 구성되어 있다 .용액조 본체로부터 퍼내어진 용액은 2개의 $3.8cm{\phi}{\times}3.8cm$ NaI(T1) 검출기가 설치된 Marinelli 비이커형의 모니터 용기로 진입되어 순환된다. 본 장치의 성능검사는 $^{241}Am-Be$ 과 $^{252}Cf$ 중성자 선원 을 사용하여 수행하였다. $^{56}Mn$ 방사능의 붕괴 곡선을 분석한 결과, $^{252}Cf$의 중성자 방출율은 1985년 11월 15일 현재 $3.71{\times}10^7\;n/s\;per\;50{mu}g$ 으로 얻어졌다.

• 한국환경과학회지
• /
• 제24권3호
• /
• pp.275-280
• /
• 2015

In order to measure the Radionuclides and Concentration, the directly grinded land samples (river soil, pine leaves and mugwort) among the environment samples around the nuclear power plant were filled in a 450 mL Marinelli beaker and weighed to obtain the dry mass ratio of the samples. Then the background and land samples were measured for 80,000 sec. The analysis of the collected land samples showed that most of them contained less radiation nuclide than the detection minimum limit in the 'Ministry of Education, Science and Technology Public Notice No. 2010-32.'In others, the natural radionuclides $^{40}K$ were detected. Of the products of nuclear reaction discharged by a nuclear reaction, $^{134}Cs$ and $^{137}Cs$ are more easily detected, and their discharge sources can be traced using the relative ratio. Although the radioactive concentration in the vicinity of Kori Nuclear Power Plant, which is more than 1,100km away from Fukushima, the Japanese nuclear accident site, continuous monitoring is needed as the radionuclides can still be accumulated in the soil or animals and plants.

• 대한방사선기술학회지:방사선기술과학
• /
• 제40권4호
• /
• pp.605-611
• /
• 2017

검출기의 구조를 PENELOPE의 코드를 사용하여 전산모사 하였다. 표준혼합시료(450, 1,000 ml)를 사용하여 다양한 밀도와 높이에 따른 저에너지(59.54 keV)부터 고 에너지(1,836.05)에 대한 측정효율과 PENELOPE 전산모사에서 구한 효율을 비교하였으며, 또한 자체흡수에 대한 효율을 보정하여 다양한 환경시료에 적용하여 검출하한치를 알아보고자 한다. 표준혼합선원의 전체에너지 피크효율 값을 적용하여 높이에 따른 효율변화를 측정치와 PENELOPE의 전산모사 값과 비교하였다. 여기서 구한 값들을 자체흡수 보정하여 구한 효율을 실제 환경시료에 적용하여 검출하한치 값들을 구하였다. 밀도보정인자는 밀도가 $0.4g/cm^3$에서 241Am(59.54 keV)의 밀도보정인자는 1.15, PENELOPE 전산모사에서는 1.153, 137CS(661.66 keV) 에서는 $1.06g/cm^3$, PENELOPE 전산모사에서는 1.064, 88Y(1,836.04 keV)에 대한 밀도보정인자는 1.03, PENELOPE 전산모사에서는 1.033으로 불확도는 1% 이내에서 잘 일치함을 확인하였다. 환경 시료의 밀도에 따른 방사능 농도는 시료량이 많을수록, 측정시간이 증가할수록 MDA(Minimum Detectable Activity) 값이 감소함을 확인할 수 있었다.

• Journal of Radiation Protection and Research
• /
• 제46권3호
• /
• pp.127-133
• /
• 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.

• 핵의학기술
• /
• 제17권1호
• /
• pp.3-6
• /
• 2013

Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

• Nuclear Engineering and Technology
• /
• 제34권6호
• /
• pp.545-552
• /
• 2002

We developed an ultra low background gamma ray spectrometer particularly suitable for experiment which require lower detection limit. The background of a germanium spectrometer is suppressed by applying active and passive shielding technique at the same time. The active shielding devices consist of plastic scintillating plates of 50 mm thick and anti-coincidence electronic system. The shielding is made of 150 mm thick walls of very low activity lead,20 mm with activity of <10 Bq/kg and 130 mm with activity of <50 Bq/kg. The observed background count rates are 1.2 $s^{-1}$ and 0.36 $s^{-1}$ without and with the active shielding, respectively, overall the energy regions from 30 keV to 3 MeV The cosmic ray induced background is suppressed by a rate of 0.8 $s^{-1}$ at the present work. The detection efficiency curve necessary to obtain the radioactivity of environmental samples has been precisely determined on the energy regions from 80 to 2000 keV with a 10$^3$ ml marinelli beaker sample, consisting of the calibrated radionuclides $^{109}$ Cd, $^{57}$ CO, $^{139}$ Ce, $^{203}$ Hg, $^{113}$ Sn, $^{85}$Sr, $^{137}$ Cs, $^{60}$ Co and $^{88}$ Y. Virtues Of the method are demonstrated by measuring the activity of $^{137}$ Cs contained in the powdered milk.