• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2570-2575
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• 2021

The exchange behaviors of hydrogen isotopes between protonated lithium metal compounds and deuterated water or tritiated water were investigated. The various protonated lithium metal compounds were prepared by acid treatment of lithium metal compounds with different crystal structures and metal compositions. The protonated lithium metal compounds could more effectively reduce the deuterium concentration in water compared with the corresponding pristine lithium metal compounds. The H⁺ in the protonated lithium metal compounds was speculated to be more readily exchangeable with hydrons in the aqueous solution compared with Li⁺ in the pristine lithium metal compounds, and the exchanged heavier isotopes were speculated to be more stably retained in the crystal structure compared with the light protons. When the tritiated water (157.7 kBq/kg) was reacted with the protonated lithium metal compounds, the protonated lithium manganese nickel cobalt oxide was found to adsorb and retain twice as much tritium (163.9 Bq/g) as the protonated lithium manganese oxide (69.9 Bq/g) and the protonated lithium cobalt oxide (75.1 Bq/g) in the equilibrium state.

• Archives of Pharmacal Research
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• 제20권6호
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• pp.637-642
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• 1997

Degradation of a compound with a hydroxyl group during the course of its diffusion across the skin was investigated. Based on the experimental findings of ashortened retention time of a degradant peak from post-diffusion samples and from the ability to evaporate radioactivity from such samples, it seems that during diffusion the parent compound degrades into a more hydrophilic product which is then oxidized. A tritium label at the carbon with a hydroxyl group was released as a tritiated water. When the post-diffusion samples were left open to the air allowing evaporation of water, there was a corresponding decrease in radioactivity of such samples. There was a linear relationship between the time left open and the fraction of radioactivity lost. When such samples were fractionated by HPLC, and then had their radioactivities measured by scintillation counting, two peaks wre identified. The first peak, which may be attributable to tritiated water, was eluted at the same retention time as the solvent front. The second peak eluted at the retention time of the parent compound. When the evaporation/loss of radioactivity experiment was repeated using a $^{14}C$-labeled compound there was no significant loss of radioactivity, indicating that the earlier loss with $^{3}H$-labeled compound was related to the formation and loas sof tritiated water.

• Journal of Radiation Protection and Research
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• 제22권2호
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• pp.97-101
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• 1997

대기중 삼중수소에 대한 국내 기초 준위를 파악하기 위하여 1995년 3월부터 12월까지 대전지역 대기중 수증기상태의 삼중수소(HTO) 및 가스상태의 삼중수소(HT)의 농도를 측정하였다. 대기시료는 삼중수소 포집장치를 이용하여 3주간 계속적으로 채취하였으며, 대기중 삼중수소는 액체섬광계수기(Liquid scintillation counter)를 이용하여 계측하였다. 대기중 HTO의 농도는 3.2-36 mBq $m^{-3}$ (평균 : 16.2 mBq $m^{-3}$)이었으며, 여름철에 높고 겨울철에 낮은 농도를 나타내었다. 이러한 경향은 대기중 절대습도의 변화와 유사하였다. 한편, 대전지역 대기 수분중삼중수소의 비방사능 농도는 0.62-3.82 Bq $L^{-3}$ 범위의 값을 나타내었으며, 대기중 HT는 35.7-48.9 mBq $m^{-3}$(평균 : 41.1 mBq $m^{-3}$)의 농도범위를 나타내었다.

• Nuclear Engineering and Technology
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• 제35권2호
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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.

• Journal of Radiation Protection and Research
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• 제46권1호
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• pp.32-34
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• 2021

• Nuclear Engineering and Technology
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• 제53권11호
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• pp.3798-3807
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• 2021

Tritium extraction from radioactively contaminated cement mortar samples was performed using heating and liquid scintillation counting methods. Tritiated water molecules (HTO) can be present in contaminated water along with water molecules (H₂O). Water is one of the primary constituents of cement mortar dough. Therefore, if tritium is present in cement mortar, the buildings and structures using this cement mortar would be contaminated by tritium. The radioactivity level of the materials in the environment exposed to tritium contamination should be determined for their disposal in accordance with the criteria of low-level radioactive waste disposal facility. For our experiments, the cement mortar samples were heated at different temperature conditions using a high-temperature combustion furnace, and the extracted tritium was collected into a 0.1 M nitric acid solution, which was then mixed with a liquid scintillator to be analyzed in a liquid scintillation counter (LSC). The tritium extraction rate from the cement mortar sample was calculated to be 90.91% and 98.54% corresponding to 9 h of heating at temperatures of 200 ℃ and 400 ℃, respectively. The tritium extraction rate was close to 100% at 400 ℃, although the bulk of cement mortar sample was contaminated by tritium.

• 약학회지
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• 제32권3호
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• pp.194-197
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• 1988

We measured the rate of water transfer across the isolated small intestine of the rat in Wiseman apparatus using tritiated water ($^3H_2O$) in drinking beverages such as electrolytes solution, fruit juice, carbonated water and barley water. Initial transfer rate of water using four beverages were determined: Electrolytes solution is the fastest and followed by barley water, carbonated water and fruit juice.

• Journal of Radiation Protection and Research
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• 제23권1호
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• pp.25-32
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• 1998

환경에서 삼중수소는 주로 HTO 형태로 존재하며, 이동성이 크므로 대기권으로 쉽게 증발한 후 광합성작용을 거쳐 식물의 영양분과 결합한 다음 먹이연쇄 과정을 통하여 최종적으로 사람에게까지 전달된다. 조직결합수(OBT)는 인체 내에서 장시간 체류할 수 있으므로 피폭선량 측면에서 지금까지 주로 고려되어진 조직자유수(TFWT)와는 다르게 인식되어야 한다. 육상생태계 내에서 OBT는 식물의 광합성 작용에 의해 주로 생성되지만 다양한 환경매체의 영향을 받기 때문에 생성량을 예측하기는 매우 어렵다. 특히 생체 내에서 결합형태에 따라 교환성 삼중수소와 비교환성 삼중수소로 구분된다. 우리나라 주요 곡류의 하나인 벼의 어린시기와 잔디에 인위적으로 HTO에 피폭시킨 후 조직결합수의 생성율을 비교하였다.

• Journal of Radiation Protection and Research
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• 제8권2호
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• pp.8-14
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• 1983

삼중수소의 단일 피폭과 만성피폭에 의한 한국인의 내부피복 선량을 삼단계형모델을 이용하여 계산하였다. 이 모델은 체내수분과 조직체 사이의 삼중 수소의 축적량을 잘 나타내 주는 것이다. 그 결과 삼단계형의 축적 반감기 9, 30과 450일을 사용한 단일 피폭의 총 선량은 1mCi/kg 섭취당 17.64mrad였고 이것의 97%는 체내수분에 있는 삼중수소에 의한 선량이고 나머지 3%는 조직내 삼중수소에 의한 것이다. 그리고 1 mCi/day의 삼중 수소를 섭취하는 만성 피폭의 경우, 총 선량은 85.5mrad/day이었다. 또한 본 연구에서는 한국인에 대한 최대허용 농도값을 선질계수 1을 사용하여 계산하였다. 그 결과, ICRP의 최대허용 농도값은 약 50%가량 낮게 평가되었으므로 한국인의 최대허용 농도값은 ICRP의 결과보다 약 50%높게 책정되어야만 한다.

• Journal of Pharmaceutical Investigation
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• 제25권3호
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• pp.223-226
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• 1995

A new method to study water uptake into biodegradable polymer was developed. Polymer was gently mixed with the tritiated buffer and the radioactivity level of the polymer due to water uptake was measured by liquid scintillation counting. The rate of water uptake was estimated from the plot of the amount of water in the device as a function of time. The technique used in this study is particularly useful for estimating water uptake of biodegradable polymers which were difficult to study by other techniques such as weight gain used for hydrogel.