• Proceedings of the Korean Society of Applied Pharmacology
• /
• 1993.04a
• /
• pp.75-75
• /
• 1993

The general pharmacological profiles of SKI 2053R were investigeted on the central nervous system, autonomic nervous system, respiratory-cardiovascular system, digestive system and other systems. SKI 2053R had no significant pharmacological effects. Pharmacokinetic studies on time-course of blood levels, tissue distribution and excretion of SKI 20S3R were performed in rats and beagle dogs after intravenous administration of $^{14}$ C-labeled SKI 2053R. The blood level of radioactivity decreased in bi-or tri-exponential manners: rapidly decreased at $\alpha$-phase but slowly decreased at $\beta$-or ${\gamma}$-phase. $^{14}$ C SKI 2053R was well distributed to all tissues except central nervous system. Tissue concentration profiles of radioactivity were almost consistent wi th those of blood, but higher than those of plasma from 1 to 168 hrs after administration. Also, these results were consistent wi th those of whole body ARG study. The urinary and fecal excretions of radioactivity within 168 hr after administration were 84-87 and 9-11 ％ of total radioactivity of $^{14}$ C-SKI 2053R administered. In lactating rats, the levels of radioactivity in the milk were significantly lower than that in the blood, but slightly higher than that in the plasma. The disapperance of the radioactivity from the milk was similar as that in the plasma.

• Nuclear Engineering and Technology
• /
• v.55 no.12
• /
• pp.4554-4560
• /
• 2023

Continuous monitoring of radioactive substances over a prolonged duration can yield crucial insights into the levels of radiation exposure through inhalation, both in the vicinity of nuclear facilities and/or general environments. In this study, we evaluated long-term measurements (2012-2022) of gross alpha-beta activities in the air in the vicinity of nuclear facilities and reference site, distribution characteristics of temporal trends and spatial fluctuations, and factors affecting radioactivity levels. The average airborne gross-α (in mBq m^-3) for onsite and off-site were 0.124 and 0.117, respectively, and the average airborne gross-β (in mBq m^-3) measurements were 1.10 and 1.04, respectively. The activity ratio (AR) of gross-α and gross-β were calculated as a ratio of 0.12. The distribution characteristics of gross-α and gross-β activities in this study area are likely influenced by the meteorological factors and variations in airborne PM concentrations rather than the operation of the nuclear facility.

• Nuclear Engineering and Technology
• /
• v.42 no.4
• /
• pp.468-473
• /
• 2010

We confirmed that the dismantling of two research reactors with thermal power of $2MW_{th}$ and $100kW_{th}$, respectively, reveals no significant difference between the radiation levels of the research reactor site and the surrounding environment far away from it, from the radiation level aspect. Radiation dose and radioactivity were measured at monitoring points around the research reactor site of the Korea Atomic Energy Research Institute (KAERI) in Seoul and comparison points 0.5 km to 3.3 km from the site. To grasp trends in the radiation levels during dismantling from the end of 2002 to the end of 2007, the gamma radiation dose rate, the accumulated dose, and the radioactivity of the strontium, tritium, and gamma isotopes were statistically treated and estimated. The averages of these items between the two groups, the research reactor site and comparison points, were assessed by applying a T-test with a significance level of 0.05. P-values found by using the T-test were from 0.12 to 0.83 where the values were much higher than the significance level. As a result, no difference was observed between the radiation levels at the research reactor site and at the comparison points by this T-test. This study showed that dismantling activity of the Korea Research Reactor of the Seoul site did not expose the public or the environment to harmful levels of radiation.

• Proceedings of the Korean Society of Applied Pharmacology
• /
• 1995.04a
• /
• 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%.

• Nuclear Engineering and Technology
• /
• v.49 no.8
• /
• pp.1752-1757
• /
• 2017

The aim of this study is to evaluate the radioactivity levels and radiological impacts of representative black sand samples collected from different locations in the Rashid area, Egypt. These samples were prepared and then analyzed using the high-resolution gamma ray spectroscopy technique with a high-purity germanium detector. The activity concentration ($A_c$), minimum detectable activity, absorbed gamma dose rate, external hazard index ($H_{ex}$), annual effective dose rate equivalent, radium equivalent, as well as external and internal hazard index ($H_{ex}$ and $H_{in}$, respectively) were estimated based on the measured radionuclide concentration of the $^{238}U$($^{226}Ra$) and $^{232}Th$ decay chains and $^{40}K$. The activity concentrations of the $^{238}U$, $^{232}Th$ decay series and $^{40}K$ of these samples varied from $45.11{\pm}3.1Bq/kg$ to $252.38{\pm}34.3Bq/kg$, from $64.65{\pm}6.1Bq/kg$ to $579.84{\pm}53.1Bq/kg$, and from $403.36{\pm}20.8Bq/kg$ to $527.47{\pm}23.1Bq/kg$, respectively. The activity concentration of $^{232}Th$ in Sample 1 has the highest value compared to the other samples; this value is also higher than the worldwide mean range as reported by UNSCEAR 2000. The total absorbed gamma dose rate and the annual effective dose for these samples were found to vary from 81.19 nGy/h to 497.81 nGy/h and from $99.86{\mu}Sv/y$ to $612.31{\mu}Sv/y$, which are higher than the world average values of 59 nGy/h and $70{\mu}Sv/y$, respectively. The $H_{ex}$ values were also calculated to be 3.02, 0.47, 0.63, 0.87, 0.87, 0.51 and 0.91. It was found that the calculated value of $H_{ex}$ for Sample 1 is significantly higher than the international acceptable limit of <1. The results are tabulated, depicted, and discussed within national and international frameworks, levels, and approaches.

• Journal of Environmental Science International
• /
• v.15 no.7
• /
• pp.689-694
• /
• 2006

To examine inshore radioactive contamination caused by nuclear power plants, nuclear testing, hospital and laboratory, both gross ${\beta}$-radioactivity and ${\upsilon}$-spectrometry were measured. The measurements were taken with the Abalone and Top shell, which had been collected from the four different sites at the coast in Jeju-do (Seongsan, Deajeong, Wimi, Dodu). The activity ranges of concentration were respectively 0.11-0.29 Bq/kg-wet for $^{90}Sr$, 0.01-0.04 Bq/kg-wet for $^{137}Cs$, 36 - 53 Bq/kg-wet for $^{40}K$ in shellfish on the Jeju island. The radioactivities of $^{90}Sr$, $^{137}Cs$ and $^{40}K$ were similar to those in sampling location of shellfish in the coastal on the Jeju island. The radioactivity of $^{90}Sr$ for the Abalone was lower level than that for Top shell. The radio- activity of $^{137}Cs$ for the Abalone was similar to that for the Top shell. But the radioactivity of $^{40}K$ for the Abalone was higher level than that for the Top shell. As a result, the gross ${\beta}$-radioactivity observed was similar to that in nature. Among radionuclides, only $^{90}Sr$, $^{137}Cs$ and $^{40}K$ were detected in a very small amount, and each was also close to the natural levels.

• Asian Pacific Journal of Cancer Prevention
• /
• v.15 no.1
• /
• pp.375-380
• /
• 2014

This study examined the incidence rates of cancer cases (averages for 2006-2010) and relationships with environmental radioactivity levels. Soil and water samples were collected from provincial and district centers of Van city and the outdoor gamma doses were determined using a portable gamma scintillation detector. Gross alpha and beta, (226)Ra, (232)Th, and (40)K activities were measured in both tap water and soil samples. Although high rates of stomach and esophagus cancers have been reported previously in Van the underlying reasons have not hitherto been defined. Incidences of cancers were highest in the Gurpmar (326.0) and Ozalp (377.1) counties (p<0.001). As to the results of the gross alpha and gross beta radioactivity measurements in the drinking water, these two counties also had high beta radionuclide levels: Gurpmar ($140mBq/dm^3$) and Ozalp ($206mBq/dm^3$). Even if within the normal range, a relation between the higher rate of the incidence of stomach and esophagus cancers with that of the higher rate of beta radionuclide activity was clear. On Spearman correlation analysis, the relation between higher beta radionuclide levels and cancer incidence was found to be statistically significant (p<0.01). According to the results of the analysis, Van residents receive an average 1.86 mSv/y annual dose from outdoor gamma radiation, ingestion of radionuclides in the drinking water, and indoor $^{222}Rn$ activity. Moreover, gross alpha and beta activities were found to be extremely high in all of the lakes around the city of Van, Turkey. Further investigations with long-term detailed environmental radiation measurements are needed regarding the relationship between cancer cases and environmental radioactivity in the city of Van.

• Journal of Radiation Protection and Research
• /
• v.42 no.1
• /
• pp.33-41
• /
• 2017

Background: Phosphate rock and its by-product are widely used in various industries to produce phosphoric acid, gypsum, gypsum board, and fertilizer. Owing to its high level of natural radioactive nuclides (e.g., $^{238}U$ and $^{226}Ra$), the radiological safety of workers who work with phosphate rock should be systematically managed. In this study, $^{238}U$, $^{232}Th$, $^{226}Ra$, and $^{40}K$ levels were measured to analyze the transport characteristics of these radionuclides in the production cycle of phosphate rock. Materials and Methods: Energy dispersive X-ray fluorescence and gamma spectrometry were used to determine the activity of $^{238}U$, $^{232}Th$, $^{226}Ra$, and $^{40}K$. To evaluate the extent of secular disequilibrium, the analytical results were compared using statistical methods. Finally, the distribution of radioactivity across different stages of the phosphate rock production cycle was evaluated. Results and Discussion: The concentration ratios of $^{226}Ra$ and $^{238}U$ in phosphate rock were close to 1.0, while those found in gypsum and fertilizer were extremely different, reflecting disequilibrium after the chemical reaction process. The nuclide with the highest activity level in the production cycle of phosphate rock was $^{40}K$, and the median $^{40}K$ activity was $8.972Bq{\cdot}g^{-1}$ and $1.496Bq{\cdot}g^{-1}$, respectively. For the $^{238}U$ series, the activity of $^{238}U$ and $^{226}Ra$ was greatest in phosphate rock, and the distribution of activity values clearly showed the transport characteristics of the radionuclides, both for the byproducts of the decay sequences and for their final products. Conclusion: Although the activity of $^{40}K$ in k-related fertilizer was relatively high, it made a relatively low contribution to the total radiological effect. However, the activity levels of $^{226}Ra$ and $^{238}U$ in phosphate rock were found to be relatively high, near the upper end of the acceptable limits. Therefore, it is necessary to systematically manage the radiological safety of workers engaged in phosphate rock processing.

• Korean Journal of Veterinary Research
• /
• v.55 no.1
• /
• pp.57-60
• /
• 2015

To investigate kinetics of free $^{177}Lu$ and $^{177}Lu$-labeled thermally cross-linked superparamagnetic iron oxide nanoparticles (TCL-SPION), suspensions were intravenously injected into the tail vein of mice at a dose of $5{\mu}Ci$/mouse or 15 mg/kg body weight, respectively. Free $^{177}Lu$ radioactivity levels were highest in kidney followed by liver and lung 1 day post-injection. $^{177}Lu$-labeled TCL-SPION radioactivity in liver and spleen was significantly higher compared to that of other organs throughout the experimental period (p < 0.05). Radioactivity in blood, brain, and epididymis rapidly declined until 28 days. Based on these results, TCL-SPION could be a safe carrier of therapeutics.

• Korean Journal of Fisheries and Aquatic Sciences
• /
• v.55 no.4
• /
• pp.431-436
• /
• 2022

For the safety assessment of microbiological and chemical hazards in katsuobushi, fifteen samples of katsuobushi were purchased from supermarkets. The contamination levels of total viable bacteria, coliforms, Escherichia coli, and nine pathogenic bacteria [Staphylococcus aureus, Salmonella spp., Listeria monocytogenes, Bacillus cereus, Vibrio parahaemolyticus, Clostridium perfringens, Enterohemorrhagic E. coli (EHEC), Yersinia enterocolitica and Campylobacter jejuni/coli] were quantitatively or qualitatively assessed. Additionally, the heavy metals (total and methyl mercury) content, radioactivity (¹³¹ I, ¹³⁴ Cs⁺ and ¹³⁷ Cs) were quantitatively assessed. Microbial and chemical analyses were performed using standard methods in Korean food code. The contamination level of total viable bacteria was 2.70 (1.18-4.42) log CFU/g. Coliforms, E. coli and S. aureus were not detected in any samples. Other eight pathogenic bacteria were negative in all samples. The contamination levels of total and methyl mercury were 0.366 (0.227-0.481) and 0.120 (0.002-0.241) mg/kg, respectively. In addition, radioactivity was not detected in any samples. The results will be helpful in revitalizing domestic use and boosting exports of katsuobushi because the microbiological and chemical safety of katsuobushi has been assured. Furthermore, the results may be used as a basis for performing chemical and microbial risk assessments of katsuobushi.