• 방사성폐기물학회지
• /
• 제19권3호
• /
• pp.367-386
• /
• 2021

The overestimation and underestimation of the radioactivity concentration of difficult-to-measure radionuclides can occur during the implementation of the scaling factor (SF) method because of the uncertainties associated with sampling, radiochemical analysis, and application of SFs. Strict regulations ensure that the SF method as an indirect method does not underestimate the radioactivity of nuclear wastes; however, there are no clear regulatory guidelines regarding the overestimation. This has been leading to the misuse of the SF methodology by stakeholders such as waste disposal licensees and regulatory bodies. Previous studies have reported instances of overestimation in statistical implementation of the SF methodology. The analysis of the two most popular linear models of the SF methodology showed that severe overestimation may occur and radioactivity concentration data must be dealt with care. Since one major source of overestimation is the use of minimum detectable activity (MDA) values as true activity values, a comparative study of instrumental techniques that could reduce the MDAs was also conducted. Thermal ionization mass spectrometry was recommended as a suitable candidate for the trace level analysis of long-lived beta-emitters such as iodine-129. Additionally, the current status of the United States and Korea was reviewed from the perspective of overestimation.

• 핵의학기술
• /
• 제14권1호
• /
• pp.111-114
• /
• 2010

양전자 방출 단층촬영은 세포의 생화학적 변화에 따른 방사성의약품의 집적 정도를 영상화함으로서 암을 조기에 진단할 수 있는 검사방법으로 알려져 있다. 이러한 집적 정도는 여러 가지 원인에 따라 발생될 수 있는 것으로 $^{18}F$-FDG 주사량, 종양의 크기, 혈중 포도당 농도 등이 있다. 본 연구에서는 집적방사능과 2D와 3D 영상 획득이 방사능 농도(kBq/mL)에 미치는 영향에 대하여 평가하고자 한다. GE Discovery STe 16 PET/CT에서 1994 NEMA PET phantom을 이용하였으며, 배후방사능과 열소의 방사능 농도비가 1:2, 1:4, 1:8, 1:10, 1:20, 1:30 표준이 되도록 하여 2D와 3D로 영상을 획득하였다. 재구성 방법으로 2D와 3D 모두에서 반복연산법으로 반복횟수 2회, 부분집합 20을 적용하였다. 그리고 CT 감쇠보정법과 획득 시간은 10분으로 설정하였다. 또한 영상분석은 열소의 중심과 배후방사능에 동일한 관심영역을 설정 한 후 각 부분의 방사능 농도를 측정하여 비교 분석하였다. 설정된 관심영역의 배후방사능과 열소의 방사능 농도 비는 2D에서 1:1.93, 1:3.86, 1:7.79, 1:8.04, 1:18.72, 1:26.90, 3D는 1:1.95, 1:3.71, 1:7.10, 1:7.49, 1:15.10, 1:23.24 값을 얻었다. 또한 표준 방사능 농도비를 기준으로 한 백분율 차이(% Difference)는 2D에서 3.50%, 3.47%, 8.12%, 8.02%, 10.58%, 11.06%로 최소 3.47%에서 최대 11.06% 차이가 있고 3D는 3.66%, 4.80%, 8.38%, 23.92%, 23.86%, 22.69%로 최소 3.66%에서 최대 23.92%까지의 차이를 나타냈다. 방사능 농도가 증가할수록 실제 집적된 방사능 농도의 차이가 커짐을 알 수 있으며, 2D가 3D보다 평균 약 10.6% 높게 집적되어 방사능 농도 변화에 영향을 적게 받는 것으로 나타났다. 따라서 임상환자의 추적 검사에서 영상 획득 방법을 변화할 시 정확한 정량 평가를 위해서 이점을 고려하여 적용하여야 한다.

• 방사선산업학회지
• /
• 제10권1호
• /
• pp.37-41
• /
• 2016

The recent prevalence of PET examinations in Korea has led to an increase in the number of cyclotrons. The medical isotope $^{18}F$ produced in most cyclotron facilities currently operating in Korea is emitted into the environment during the production of [$^{18}F$]FDG, a cancerdiagnosis reagent. The amount of [$^{18}F$]FDG synthesized determines the radioactive concentration of $^{18}F$ in the exhaust. At some facilities, this amount temporarily exceeds the emission limit. In this study, we evaluated the $^{18}F$ radioactivity concentration in the exhaust from the cyclotron facility at Chosun University. The $^{18}F$ radioactivity concentration was measured using an air sampler and a HPGe semiconductor detector. The measurements showed that the radioactive concentration of $^{18}F$ in the exhaust at the cyclotron facility at Chosun University was the highest during [$^{18}F$]FDG synthesis but remained under the legal limit of $2,000Bq\;m^{-3}$.

• Journal of Radiation Protection and Research
• /
• 제44권3호
• /
• pp.118-126
• /
• 2019

Background: Government conducts environmental radioactivity surveillance for verification purpose around nuclear facilities based on the Nuclear Safety Law and issues a surveillance report every year. This study aims to evaluate the short and the long-term fluctuation of radionuclides detected above MDC and their origins using concentration ratios between these radionuclides. Materials and Methods: Sample media for verification surveillance are air, rainwater, groundwater, soil, and milk for terrestrial samples, and seawater, marine sediment, fish, and seaweed for marine samples. Gamma-emitting radionuclides including $^{137}Cs$, $^{90}Sr$, Pu, $^3H$, and $^{14}C$ are evaluated in these samples. Results and Discussion: According to the result of the environmental radioactivity verification surveillance in the vicinity of nuclear power facilities in 2017, the anthropogenic radionuclides were not detected in most of the environmental samples except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples. Radioactivity concentration ratios between the anthropogenic radionuclides ($^{137}Cs/^{90}Sr$, $^{137}Cs/^{239+240}Pu$, $^{90}Sr/^{239+240}Pu$) were similar to those reported in the environmental samples, which were affected by the global fallout of the past nuclear weapon test, and Pu atomic ratios ($^{240}Pu/^{239}Pu$) in the terrestrial sample and marine sample showed significant differences due to the different input pathway and the Pu source. Radioactive iodine ($^{131}I$) was detected at the range of < $5.6-190mBq{\cdot}kg-fresh^{-1}$ in the gulfweed and sea trumpet collected from the area of Kori and Wolsong intake and discharge. A high level of $^3H$ was observed in the air (Sangbong: $0.688{\pm}0.841Bq{\cdot}m^{-3}$) and the precipitation (Meteorology Post: $199{\pm}126Bq{\cdot}L^{-1}$) samples of the Wolsong nuclear power plant (NPP). $^3H$ concentration in the precipitation and pine needle samples showed typical variation pattern with the distance and the wind direction from the stack due to the gaseous release of $^3H$ in Wolsong NPP. Conclusion: Except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples, anthropogenic radionuclides were below MDC in most of the environmental samples. Overall, no unusual radionuclides and abnormal concentration were detected in the 2017's surveillance result for verification. This research will be available in the assessment of environment around nuclear facilities in the event of radioactive material release.

• 한국응용약물학회:학술대회논문집
• /
• 한국응용약물학회 1995년도 춘계학술대회
• /
• pp.108-108
• /
• 1995

Pharmacokinetic studies on time-course of blood levels, tissue distribution, and excretion of G009, a potential hepatoprotective agent, were performed in male rats after a single oral dose(20mg/kg) of $\^$14/C-labelled G009. The radioactivity concentrations in plasma during 0～3 hours are low, but subsequently increase to a maximum at 12 hours after dosing. $\^$14/C-G009 was well distributed to all tissue. Tissue concentration profiles of radioactivity vary among tissues on time-course after administration. G009(single oral dosage) was distributed and/or absorbed at gastric intestines and excretional organs for initial time of 0-7 hours, and distributed to most tissue at 12-24 hours. In special, the concentration of radioactivity in tiller at 48 hours were 1% of total radioactivity of $\^$14/C-G009 administered. The expired air, urinary and fecal excretion of radioactivity within 24hours after administration were 61.5%, 1.9% and 21.2% of total radioactivity of $\^$14/C-G009 administered. The biliary excretion of radioactivity in rat increased slightly for 0-6 hours after administration. The biliary excretion of radioactivity within 48hours were 1.97%.

• 한국환경과학회지
• /
• 제12권6호
• /
• pp.677-688
• /
• 2003

The purpose of this study was to predict occurrence of earthquakes in Korea by measuring the concentration of radon radioactivity in the air and in the underground water. Two monitoring systems of radon concentration detection in the air were installed in Seoul, East Coast area, whereas of radon concentration in the underground water in Kyungju area during December, 1999 to June, 2001. The distribution of radon concentration in the air in Seoul is as follows Winter(10.10 $\pm$ 2.81 Bq/㎥), autumn(8.41 $\pm$ 1.35 Bq/㎥), summer(5.83 $\pm$ 0.05 Bq/㎥) and spring (5.34 $\pm$ 0.44 Bq/㎥), whereas the distribution of radon in the air in the East Coast area showed some difference as follows : autumn (14.08 $\pm$ 5.75 Bq/㎥), Summer (12.04 $\pm$ 0.53 Bq/㎥), Winter (12.02 $\pm$ 1.40 Bq/㎥) and spring (8.93 $\pm$ 0.91 Bq/㎥). In the meanwhile, the distribution of radon in the water is as follows : spring (123.59 $\pm$ 16.36count/10min), Winter (93.95 $\pm$ 79.69counter/10min), autumn (68.96 $\pm$ 37.53counter/10min) and spring (34.45 $\pm$ 9.69counter/10min). The daily range of the density of radon concentration in Seoul and East Coast area was between 5.51 Bq/㎥ - 9.44 Bq/㎥, 7.15 Bq/㎥ - 15.27 Bq/㎥, respectively. Correlation of the distributions of radon concentrations in the air and in underground water with earthquake showed considerable variations of radon concentration before the occurrence of the earthquake. The results suggested that radon radioactivity seemed to be helpful for the prediction of the occurrence of earthquake.

• 방사선산업학회지
• /
• 제17권4호
• /
• pp.471-479
• /
• 2023

In In-situ radioactivity measurement techniques, efficiency calibration models use predefined models to simulate a sample's geometry and radioactivity distribution. However, simplified efficiency calibration models lead to uncertainties in the efficiency curves, which in turn affect the radioactivity concentration results. This study aims to develop an efficiency calibration optimization methodology to improve the accuracy of in-situ gamma radiation measurements for byproducts from industrial facilities. To accomplish the objective, a drive mechanism for rotational measurement of an byproduct simulator and a sample was constructed. Using ISOCS, an efficiency calibration model of the designed object was generated. Then, the sensitivity analysis of the efficiency calibration model was performed, and the efficiency curve of the efficiency calibration model was optimized using the sensitivity analysis results. Finally, the radiation concentration of the simulated subject was estimated, compared, and evaluated with the designed certification value. For the sensitivity assessment of the influencing factors of the efficiency calibration model, the ISOCS Uncertainty Estimator was used for the horizontal and vertical size and density of the measured object. The standard deviation of the measurement efficiency as a function of the longitudinal size and density of the efficiency calibration model decreased with increasing energy region. When using the optimized efficiency calibration model, the measurement efficiency using IUE was improved compared to the measurement efficiency using ISOCS at the energy of ²²⁸Ac (911 keV) for the nuclide under analysis. Using the ISOCS efficiency calibration method, the difference between the measured radiation concentration and the design value for each simulated subject measurement direction was 4.1% (1% to 10%) on average. The difference between the estimated radioactivity concentration and the design value was 3.6% (1~8%) on average when using the ISOCS IUE efficiency calibration method, which was closer to the design value than the efficiency calibration method using ISOCS. In other words, the estimated radioactivity concentration using the optimized efficiency curve was similar to the designed radioactivity concentration. The results of this study can be utilized as the main basis for the development of regulatory technologies for the treatment and disposal of waste generated during the operation, maintenance, and facility replacement of domestic byproduct generation facilities.

• 약학회지
• /
• 제41권3호
• /
• pp.335-344
• /
• 1997

The absorption, distribution and excretion of $^{14}C$ labeled YH1885 {5,6-Dimethyl-2(4-fluorophenylamino)-4-(1-methyl-1,2,3,4-tetrahydroisoquinolin-2-yl)pyrimidine hydroc hloride), a new proton pumpinhibitor, were investigated in rats after a single administration of $^{14}C$-YH1885. 1. After intravenous administration of 5mg/kg, the blood level of radioactivity declined in a biphasic fashion with the mean terminal elimination half-life of 12.4hr. 2. After oral administration of 20mg/kg, the maximum blood level of radioactirity was reached at 4.0hr in female rats. The blood level of radioactivity-time profiles in male and female rats were similar, and the absorptionof $^{14}C$-YH1885 was not affected by food. 3. Appproximately 89% and 1% of radioactivity of the total dose were excreted in feces and urine, respectively. 4. Biliary excretion of radioactivity was 47.9% of the dose. Enterohepatic circulation of radioactivity was 49.6%. 5. Radioactivity was excreted maily into feces via bile. 6. The concentration of radioactivity in most tissues reached the peak level at 4.0hr after dosing, and then declined. Autoradiograms of male rats showed that the radioactivity levlels in the fat, harder's gland, liver and G-Itract were higher than those in the other tissues and the elimination of radioactivity from fat and liver was slow. 7. Autoradiograms of a pregnant rat showed that radioactivity was transferred to mammary gland, placenta and fetus. The radioactivity level in the mammary gland was higher than that in the blood.

• 대한핵의학회지
• /
• 제16권1호
• /
• pp.55-61
• /
• 1982

Biodistribution studies has been carried out to elucidate the cause of poor bone imagings often encountered in using $methylenediphosphonate(MDP)-^{99m}Tc$ and to establish effective conditions in using the popular bone imaging agent. After 150 minutes from the I.V. injection of $MDP-^{99m}Tc$ to mice, the radioactivities accumulated at bone(B), liver(L), and stomach(S) were counted. The radiochemical purity (RCP), the volume, the radioactivity concentration and the amount of radioactivity of $MDP-^{99m}Tc$ were controlled. Data were expressed either in %cpm/g organ or % cpm/organ. The organ distribution ratios(B/L and B/S) were correlated with the RCP, the volume of injection, the radioactivity concentration etc. Results indicated that the RCP plays a major role in biodistributions. High radioactivity concentration and injection of a small amount is recommended. Negligible effect was observed with the amount of radioactivity. It has been confirmed that the up-to-date methods of RCP determinations cannot sensitively detect the sharply affecting trace impurities. A particular biodistribution pattern of crossed B/L and B/S lines was observed in case of using $MDP-^{99m}Tc$ of low RCP. In such a case, rather a higher dosage would be effective for improving the contrast between bone and liver.

• 방사성폐기물학회지
• /
• 제21권4호
• /
• pp.481-487
• /
• 2023

Concerning the apprehensions about naturally occurring radioactive materials (NORM) residues, the International Atomic Energy Agency (IAEA) and its member nations have acknowledged the imperative to ensure the radiation safety of NORM industries. Residues with elevated radioactivity concentrations are predominantly produced during NORM processing, in the form of scale and sludge, referred to as technically enhanced NORM (TENORM). Substantial quantities of TENORM residues have been released externally due to the dismantling of NORM processing factories. These residues become concentrated and fixed in scale inside scrap pipes. To assess the radioactivity of scales in pipes of various shapes, a Monte Carlo simulation was employed to determine dose rates corresponding to the action level in TENORM regulations for different pipe diameters and thicknesses. Onsite gamma spectrometry was conducted on a scrap iron pipe from the titanium dioxide manufacturing factory. The measured dose rate on the pipe enabled the estimation of NORM concentration in the pipe scale onsite. The derived action level in dose rate can be applied in the NORM regulation procedure for on-site judgments.