• Journal of Radiation Protection and Research
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• v.34 no.4
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• pp.184-189
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• 2009

In pressurized heavy water reactors, workers who enter radiation controlled areas must submit their urine samples to health physicists after radiation work; these samples are then used to monitor internal radiation exposure from tritium intake. This procedure assumes that the samples submitted represent tritium concentration inside the body at equilibrium. According to both technical reports from the International Commission on Radiological Protection and experimental results from Canadian nuclear utilities, tritium inside the body generally reaches equilibrium concentration after approximately 2-3 hours of intake. In practice, urine samples can be submitted either before the 2 hours mark or after several hours of radiation work because of the numerous tasks that workers must perform and their frequent entries during nuclear power plant maintenance. In this paper, tritium concentration in workers' urine samples was measured as a function of time submitted after radiation work. Based on the measurement results, changes in the tritium concentration inside the body and its effect on internal dose assessment were then analyzed. As a result, it was found that tritium concentration reaches equilibrium concentration before the 2 hours mark for most workers' urine samples.

• 한국지구물리탐사학회:학술대회논문집
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• 2003.11a
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• pp.344-351
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• 2003

Hydrogeological survey and geochemical analysis were carried out in Phra Yun area, Northeast Thailand, which is a typical salt-affected area for an understanding of hydrogeological groundwater behaviours. Geological survey reveals the presence of G1 and F1 faults. Electromagnetic ground conductivity prospecting shows that the high conductivity zones of 15 mS/cm or more are distributed at underground of the G1 and F1 faults where saline groundwater is discharged. The distribution patterns of tritium concentration show that high tritium concentration zones of groundwater were recharged from pond and river. On the assumption that the annual average tritium concentration of precipitation in Northeast Thailand is same as tritium concentration of precipitation in Tokyo and groundwater flows as piston flow, the age of recharging precipitation of groundwater with 15 TU in 1997 could be estimated at 1967-1970 years. The velocity of groundwater flow was calculated to be $5.3{\times}10^{-7}\;m/s\;and\;2.1{\times}x10^{-6}\;m/s$ respectively from a duration time of 30 years and distance of groundwater flow 500m -2000m from the pond and river to the investigation wells. Because the estimated values of velocity of groundwater flow are compatible with the hydraulic conductivities, it is considered that 30 years is a reasonable period for recharging groundwater.

• Analytical Science and Technology
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• v.23 no.2
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• pp.161-164
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• 2010

The concentration of the tritium in precipitation from 2007 to 2009 has been analyzed for using tracer of groundwater study. The samples were collected monthly at Daejeon. The tritium concentrations in precipitation were ranged from 4.2 TU to 18.6 TU. The contents were higher at spring and fall season and lower at summer and winter season. The weighted average tritium content in precipitation was $7.85{\pm}0.46\;TU$.

• Journal of the Korean Chemical Society
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• v.40 no.6
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• pp.436-444
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• 1996

The characteristics of water have been studied for 1 year by means of relationships between tritium and total dissolved solid(TDS), tritium and conductivity, tritium and chloride, and tritium and total hardness for 15 springs in the vicinity of Jeonju city of Korea. From the results of the study, the springs were divided into four characteristic groups, but the characteristics of most springwaters studied were similar to those of rainfall. Fifteen springwaters were evaluated to see if those are tasty and healthy using the Hashimoto's Mineral Balance Index. As a result, only one spring (J-4) was found as tasty and healthy.

• Journal of Radiation Industry
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• v.2 no.3
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• pp.141-148
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• 2008

Beta rays emitted from tritium in titanium tritide film were simulated with cathode rays of a scanning electron microscope to investigate the effect of beta rays from tritium on semiconductor devices. The cathode ray currents, which vary with the change of applied energy and beam spot size, were measured with Faraday cup. The current from the semiconductor device irradiated with cathode rays at various conditions was measured. The cathode ray current increased with the increase of spot size to a maximum then decreased when the spot sized increased further. The magnitude of current produced in the semiconductor device is proportional to the magnitude of cathode ray current. The magnitude of cathode ray current at each energy level was matched to the intensity of beta ray to simulate the tritium beta ray spectrum. Then the semiconductor characteristics were analyzed with I-V curves.

• Nuclear Engineering and Technology
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• v.52 no.2
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• pp.323-327
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• 2020

In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed. In the proposed design, it is adequate to enrich up to 40% ⁶Li. Total tritium breeding ratio of 1.12 is achieved. The temperature of helium as coolant gas never exceed 687℃. As regards the tolerable temperature of beryllium (650℃), the design of blanket module is done in the way that beryllium temperature never exceed 600℃. The main feature of this design indicates the temperature of helium coolant is higher than other proposed models for blanket module, therefore power of electricity generation will increase.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.46-50
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• 1996

Tritium dose management is an important aspect of the radiation protection program at CANDU type reactor sites. This paper describes the bioassay and dosimetry of tritium at CANDU reactor sites, especially for Wolsung Nuclear Power Plant. It presents a compilation of information drawn from published papers, technical reports, international and national guidelines as well as practical experience both in Korean and Canadian CANDU Nuclear Power Plants. The implementation of this program would provide a technical basis for demonstrating to workers, managers and regulators that tritium bioassay measurements, dose calculations and records should be of acceptable quality and should meet overall radiation protection program objectives.

• Nuclear Engineering and Technology
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• v.35 no.2
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• pp.171-177
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• 2003

A dynamic compartment model was required for the prediction of radiological consequences of the tritiated vapor released from the nuclear facility after an accident. A computer code, ECOREA-T, was developed by incorporating the unit models for the evaluation of tritium behavior in the environment. Dry deposition of tritiated vapor from the atmosphere to the soil was calculated using a deposition velocity. Transport of tritium from the atmosphere to the plant was calculated using a specific activity model, and the result was compared with the Belot's analytic solution. Root uptake of tritiated water from the soil and formation of OBT from T were considered in the model. The ECOREA-T code was verified by comparing the results from the other computer codes using a scenario developed through BIOMOVS II study. The results showed good agreements.

• Transactions of the Korean hydrogen and new energy society
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• v.23 no.1
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• pp.56-64
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• 2012

The ITER fuel cycle is designed for DT operation in equimolar ratio. It involves not only a group of fuelling system and torus cryo-pumping system of the exhaust gases through the divertor from the torus in tokamak plant, but also from the exhaust gas processing of the fusion effluent gas mixture connected to the hydrogen isotope separation in cryogenic distillation to the final safe storage & delivery of the hydrogen isotopes in tritium plant. Tritium plant system supplies deuterium and tritium from external sources and treats all tritiated fluids in ITER operation. Every operation and affairs is focused on the tritium inventory accountancy and the confinement. This paper describes the major fuel cycle processes and interfaces in the tritium plant in aspects of upcoming technologies for future hydrogen and/or hydrogen isotope utilization.

• Transactions of the Korean hydrogen and new energy society
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• v.24 no.2
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• pp.121-127
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• 2013

Tritium was attracted with high energy source in neutron fusion energy systems. A number of research was performed in tritium storage materials. The Korea was raised storage and delivery systems (SDS) of international thermonuclear experimental reactor (ITER) research. However, bottles of SDS would be important because of stability. The bottles have a welding zone, this zone will be vulnerable to hydrogen embrittlement. This zone have a high thermodynamic energy and heat deterioration. Therefore bottles were studied about hydrogen embrittlement to retain stability. The heat treatment of hydrogen was carried under pressure-composition-temperature (PCT) apparatus because of checking at real time. And then, mechanical properties were evaluated by tensile test and hardness test. In results of this study, hydrogen atmosphere condition is very important by tensile test and kinetics test. The samples were evaluated, that is more weak hydrogen pressure, increasing temperature and time. This results could be useful in SDS bottle designs.