• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.172-181
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• 2005

Collection Efficiency of a tritium bubbler being used at domestic nuclear power plants was studied. Equilibrium is attained while tritium vapour in air passes through the bubbler. When a lot of gas sample passes through the bubbler, the tritium concentration of water is raised and volume of water is decreased or increased. These phenomena give effect to the collection efficiency. Estimation of the tritium concentration of the water agreed with our experiments. If relative humidity is higher than 0.5, the efficiency becomes lower than 1 and if relative humidity is lower than 0.5, the efficiency becomes higher than 1, provided collected tritium is evaluated with original volume of the water. Though the relative humidity is riot 0.5, the efficiency can be maintained near 1 by making $\frac{saturated\; water\; vapour(cm^3_w)\times volume \; of \; gas \; sample(cm^3)}{volume\; of\; water(cm^3)}$ small

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.539-543
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• 2003

The objective of this to improve the reliability of the safety evaluation code for Wolsong Tritium Removal Facility(WTRF) which is on the development for environmental assessment. To achieve this, tritium concentrations calculated in the Wolsong Units of this study are compared with that of the existing reference. As the result, the tritium concentration in each Wolsong nuclear power plant unit just before operating WTRF is 60.9Ci/kg, 36.3Ci/kg, 30.0Ci/kg, 26.5Ci/kg under the assumption that the WTRF begins operation in 2005, respectively. This result is almost same with that of the existing reference. But the reducing rate of tritium concentration in the moderator is faster than that of the reference result Finally it is expected to drop below 10Ci/kg after WTRF operation. And this result is also similar with that of the existing reference.

• Journal of Radiation Protection and Research
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• v.23 no.1
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• pp.25-32
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• 1998

Tritium is released into the environment as various form but HTO is most relevant to the incorporation of tritium into living organisms and to the formation of OBT. Tritiated compounds may be transported to humans via several tropic levels. Retention times of organically bound tritium in organisms are considerably longer than those of tritiated water, which has significant consequences on exposure dose estimation. It is rather difficult to predict the amount of OBT produced by the photosynthetic process of plants because it may be influenced by a multitude of environmental factors and plant parameters. Tritiated organic matters are classified as the exchangeable or nonexchangeable bound tritium according to the bound form. After short term HTO exposure in plants, the formation and uptake of OBT were evaluated.

• Analytical Science and Technology
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• v.20 no.5
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• pp.419-423
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• 2007

Environmental low level tritium analysis was studied using liquid scintillation counter(LSC) and electrolytic enrichment method. To obtain low level blank count, various counting vials were investigated. Among them, teflon coated PE vial had a lower blank count rate (1.86 cpm) and we obtained 2.01 Bq/L detection and tritium separation factor was above 20. LSC counting efficiency obtained $28.70{\pm}0.27%$ using the NIST tritium standard water sample.

• 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.

• Bulletin of the Korean Chemical Society
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• v.30 no.12
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• pp.3095-3097
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• 2009

• Journal of Radiation Protection and Research
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• v.33 no.3
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• pp.113-120
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• 2008

In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it's transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/$H_2-g$. This level is three order of lower than the regulation value of 56 Bq/$H_2-g$ from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.

• Journal of Radiation Protection and Research
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• v.17 no.2
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• pp.25-35
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• 1992

To evaluate tritium level in some environmental samples, tissue-free water tritium (TFWT) and tissue-bound tritium (TBT) were analyzed in rices, chinese cabbages and pine needles collected at 12 locations in Korea. The TFWT was recovered by freeze-drying of the samples and the TBT was obtained in the form of water by combustion of the dried samples. Tritium was measured by liquid scintillation counter. The concentrations of TFWT were in the range of $0.96{\sim}3.96 Bq/1,\; 0.83{\sim}3.40 Bq/1\;and\;1.02{\sim}3.01 Bq/1$ in rices, chinese cabbages and pine needles, respectively. The mean specific activity ratios (TBT/TFWT) were 0.94, 1.71 and 1.39 in rices, chinese cabbages and pine needles, respectiviely. This excess TBT in the samples may be attributed to the fact that the residence time of TBT in the plant is longer than that of TFWT. The specific activity ratio depends on the plant species, the exposed time to tritiated atmosphere, atmospheric moisture, temperature and diffusion factor.

• Progress in Medical Physics
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• v.5 no.1
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• pp.75-85
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• 1994

As we enter the 2000s, there are four nuclear power units of the pressurized heavy water reactor-type in the commercial operation at the Wolsung Nuclear Power Plant(NPP) site where a larger amount of tritium ($\^$3/H) is released inevitably to the site environment. This radioctive nuclide is easily distributed throghout our environment because of its ubiquitous form as tritiated water (HTO) and its persistence in the environment. Tritum has certain characterisitics that present unique challenges for beta radiation dosimety and health risk assesment. In this paper, therefore, a variety of matters on tritium are considered and reviewed in terms of its characteristics and sources, metabolism and dosimetry, microdosimetry, radiobiology, risk assessment, and transport and cycling in the environment, etc.

• 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.