• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.951-955
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• 1995

핵융합반응에 삼중수소는 필수연료이다. 삼중수소의 전이반응에 효율적인 고분자촉매를 합성제조하여 반응탑에서 전이반응실험을 수행하였다. 고분자촉매는 삼중수소 전이반응에 유용한 활성을 나타냄이 확인되었고, 기체유속 및 반응온도가 증가함에 따라 전이반응은 촉진되는 것이 밝혀졌다.

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.186-187
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• 2011

• Journal of Radiation Protection and Research
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• v.21 no.2
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• pp.107-115
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• 1996

An electrolytic enrichment technique was used to measure low levels of tritium in seawater around the Korean peninsula. Tritium concentrations were determined for surface seawater samples collected from the East Sea, the South Sea, and the Yellow Sea. The tritium concentrations in surface seawater samples from the study area ranged from $0.12 BqL^{-1}\;to\;1.50BqL^{-1}$ with a mean value of $0.60{\pm}0.35 BqL^{-1}$. The means of the tritium concentration were $0.54{\pm}0.30 BqL^{-1}$ for the East Sea, $0.48{\pm}0.35 BqL^{-1}$ for the South Sea, and $0.77{\pm}0.32 BqL^{-1}$ for the Yellow Sea. The tritium concentrations in the sea areas did not show much difference no matter where the samples were taken. Due to the limited number and distribution of sampling points, no systematic change in tritium levels with latitude was observed. Measured tritium levels were similar to those observed in other data collected near Japan, but higher than mid-Pacific Ocean measurements.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.4
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• pp.319-328
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• 2005

This paper describes a compartment dynamic model for evaluating the contamination level of kritium in agricultural plants exposed by accidentally released tritium. The present model uses a time-dependent growth equation of plant so that it can predict the effect of growth stage of plant during the exposure time. The model including atmosphere, soil and plant compartments is described by a set of nonlinear ordinary differential equations, and is able to predict time-dependent concentrations of tritium in the compartments. To validate the model, a series of exposure experiments of HTO vapor on Chinese cabbage and radish was carried out at the different growth stage of each plant. At the end of exposure, the tissue free water(TFWT) and the organically bound tritium(OBT) were measured. The measured concentrations were agreed well with model predictions.

• Journal of Radiation Protection and Research
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• v.22 no.2
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• pp.119-125
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• 1997

PHWR achieves high neutron economy by adopting heavy water as its moderator and coolant. On the other hand it permits much tritium generation, compared to LWR, due to the neutron capture reaction of deuterium in heavy water. Meanwhile in the reactor core, $^3He formed as the result of-decay of tritium, captures a thermal neutron and transforms to tritium again. The existing calculation models on tritium generation in PHWR neglect the contribution of $^3He$ in both moderator and coolant due to its relatively low solubility. However the neutron capture cross-section of $^3He$ is almost $1.6{\times}10^7$ times as large as that of deuterium. That means that the dissolved amount of 0.03 ppm of $^3He$ in heavy water is enough to generate the same amount of tritium as that generated by the deuterium of total heavy water in the system. This study dealt with the contribution of $^3He$ to tritium generation. As a sample case, the contribution of $^3He$ to the tritium generation in Wolsong #1 was evaluated and compared to the measured values. According to the result of this study, it is concluded that $^3He$ in coolant contributes very much to the tritium generation but that in moderator shows negligible effects due to the low solubility and $^4He$ cover gas. At the beginning of the plant operation, the contribution of $^3He$ is slightly greater than the measured value but agrees well with the measured as the operating time increases.

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.210-211
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• 2009

• 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

• 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.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.859-864
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• 1995

중수형발전로의 가동에 따라 중수는 삼중수소로 오염된다 오염된 중수의 정화에 적합한 공정으로 평가되는 기액촉매교환과 초저온증류공정으로 이루어진 촉매복합공정에 대하여 탑내의 유속비 및 이론단수의 변화에 따른 촉매탑과 증류탑에서의 삼중수소 제거율 및 농축률 그리고 탑내의 수소동위원소의 농도분포변화를 Newton-Raphson 방법을 사용하여 전산모사를 수행하여 구하였다. 이러한 해석은 본격적 최적화 설계의 기초입력자료로 활용될 것이다.

• 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.