• Analytical Science and Technology
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• v.17 no.3
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• pp.251-262
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• 2004

It is for the purpose of investigating the tritium distribution in the leachates, the raw and treated leachates and the condensates of the methane gas, which have occurred from domestic solid waste landfills. Also it aims to measure the tritium distribution level on the colloid size of the leachates, the raw and treated leachates. It was found that the major inorganic contaminants of the leachates were Na, K, Ca, Mg, $NH{_4}^+$-N and $Cl^-$. The mean tritium level of the raw leachates of the investigated 13 landfill sites for 6 months was 17 ~ 1196 TU. It corresponded to a several scores or hundreds of magnitude higher value than that of the normal environmental sample level except for two landfill sites. Also such a high concentration of the tritium was found in the treated leachates and methane gas condensates as well. Nevertheless it is important to emphasize that the tritium level which was found in this research is about 100 times lower than the tritium limit for the drinking water quality. And most of the tritium existed in the dissolved colloid of the leachate of which the colloid size is below $0.45{\mu}m$. Also, according to the tritium analysis results of the leachates after filtration with $0.45{\mu}m$ membrane filter for some landfills, it is likely that some tritium of the leachate would be distributed in a colloid size over $0.45{\mu}m$. In general the relationship between the tritium and other contaminants in the raw leachate was low, but it was relatively high between the tritium and TOC. However, the tritium content in the leachate had no meaningful relationship with the scale, hydrological characteristics and age of the landfill.

• Journal of Radiation Industry
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• v.17 no.4
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• pp.437-442
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• 2023

This study conducted a comparative analysis of dose evaluations for ingestion of animal products based on data from nuclear power plants in the Republic of Korea, using methodologies from the Republic of Korea, 'IAEA TRS-472', and 'CSA N288.1:14'. The research focused on tritium, the most significant constituent among the gaseous and liquid radioactive emissions. The combined evaluation of tritium, in the form of tritiated water (HTO) and organically bound tritium (OBT), yielded results of 1.143 μSv y^-1 for the Republic of Korea, 0.965μSv y^-1 for 'TRS-472', and 0.886μSv y^-1 for 'N288.1:14'. Despite the Republic of Korea's guidelines not considering OBT, the evaluation results for the Republic of Korea were higher compared to other methodologies. This discrepancy was attributed to the unique approach of not considering the moisture content per individual in the calculations of plant and feed concentration in the Republic of Korea and the simultaneous consideration of specific-activity model and transfer model. The study highlights the necessity of developing dose evaluation models tailored to regional characteristics and underscores the importance of including OBT in these evaluations.

• Journal of Radiation Industry
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• v.18 no.3
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• pp.155-166
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• 2024

In this study, a liquid scintillation spectrometer was developed for online continuous monitoring of tritium nuclides in water. The device consists of two photoelectron multiplier tubes (PMT), a simultaneous counting circuit, and a signal processing unit including a multi-channel analyzer (MCA). As a method to verify the performance of the equipment developed in this study, samples were prepared using a standard source, and the spectrum of tritium was measured to evaluate the detector characteristics such as efficiency, background (BKG), and minimum detectable activity (MDA). To evaluate the effect of pretreatment on tritium radioactivity measurement results, the MDA of water (seawater and groundwater) samples before and after pretreatment was calculated and compared. The results of the evaluation confirmed the satisfaction of the reference values of the Nuclear Safety Commission's "Discharge Control Standard in Drainage Water" and the World Health Organization's (WHO) "Tritium Radioactivity Concentration for Drinking Water Standards". The liquid scintillation spectrometer developed in this study, with or without pretreatment, confirmed detection performance equivalent to 1/100th of the discharge control standard for drainage water (40,000 Bq L^-1) and the WHO's drinking water standard for tritium radioactivity (10,000 Bq L^-1).

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.332-332
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• 1998

• Journal of the Korean Society of Groundwater Environment
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• v.2 no.2
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• pp.72-77
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• 1995

Flow times of the groundwater in the gneiss near Samkwang mine in Korea were estimated through the development of a mathematical model, the field hydraulic tests, and the analysis of tritium concentration of the groundwater and rainfall sampled in the study positions. Results of this study we as follows: (1) The mathematical model to calculate the age of groundwater was developed considering the tritium concentrations of rainfall precipitated in the studied area for period 1961 to 1993. (2) The ages of the groundwater in the tunnel 44, 92, 102, and 205 m below the surface were estimated at 2, 0, 4.0, 4.5, and 9.0 years, respectively. These results were verified by the data on the tritium concentrations of the groundwater in the tunnel for period 1991 to 1993.

• The Korean Journal of Pharmacology
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• v.30 no.2
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• pp.145-152
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• 1994

As it has been reported that the depolarization induced acetylcholine(ACh) release is modulated by activation of presynaptic $A_1-adenosine$ heteroreceptor and various lines of evidence indicate the $A_2-receptor$ is present In hippocampus, this study was undertaken to delineate the role of adenosine receptors on hippocampal ACh release. Slices from the rat hippocampus were equilibrated with $[^3H]-choline$ and the release of the labelled product, $[^3H]-ACh$, which evoked by electrical stimulation(3 Hz, $5\;Vcm^{-1}$, 2 ms, rectangular pulses) was measured, and the influence of various agents on the evoked tritium outflow was Investigated. Adenosine$(0.3{\sim}100\;{\mu}M)$ and CPA$(0.1{\sim}30\;{\mu}M)$ decreased the $[^3H]-ACh$ release in a dose-dependent manner without changing the basal rate of release. DPCPX$(1{\sim}10\;{\mu}M)$, a selective $A_1-receptor$, antagonist, increased the $[^3H]-ACh$ release in a dose related fashion with slight increase of basal tritium release. And the effects of adenosine and CPA were significantly inhibited by $DPCPX(2\;{\mu}M)$ treatment. CPCA, a specific $A_2-agonist$, in concentration ranging from 0.3 to 30 ${\mu}M$, decreased the evoked tritium outflow, and these effects were also abolished by $DPCPX(2\;{\mu}M)$ treatment. But the CPCA effects were not affected by $DMPX(2\;{\mu}M)$, a specific Aa-antagonist, treatment. However, CGS 21680c, a recently introduced potent $A_2-agonist$, in concentration ranging from 0.1 to $10{\mu}M$, did not alter the evoked tritium outflow. These results indicate that the decrement of the evoked ACh release by adenosine is mediated by $A_1-heteroreceptor$, but $A_2-adenosine$ receptor is not involved in ACh release in the rat hippocampus.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.286-286
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• 1998

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.331-331
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• 1998

• Journal of Radiation Protection and Research
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• v.46 no.1
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• pp.32-34
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• 2021

• Journal of Radiation Protection and Research
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• v.34 no.2
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• pp.87-94
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• 2009

Tritium is the one of the dominant contributors to the internal radiation exposure of workers at pressurized heavy water reactors (PHWRs). This nuclide is likely to release to work places as tritiated water vapor (HTO) from a nuclear reactor and gets relatively easily into the body of workers by inhalation. Inhaled tritium usually reaches the equilibrium of concentration after approximately 2 hours inside the body and then is excreted from the body with a half-life of 10 days. Because tritium inside the body transports with body fluids, a whole body receives radiation exposure. Internal radiation exposure at PHWRs accounts for approximately 20-40% of total radiation exposure; most internal radiation exposure is attributed to tritium. Thus, tritium is an important nuclide to be necessarily monitored for the radiation management safety. In this paper, metabolism for tritium is established using its excretion rate results in urine samples of workers at PHWRs and an effective half-life, a key parameter to estimate the radiation exposure, was derived from these results. As a result, it was found that the effective half-life for workers at Korean nuclear power plants is shorter than that of International Commission on Radiological Protection guides, a half-life of 10 days.