• 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.

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.280-281
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• 2009

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.453-457
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• 1996

월성원자력발전소에서 생성되는 삼중수소는 핵융합로의 필수원료물질이다. 삼중수소 분리반응 탑에 소요되는 다단탑의 단수와 최적운전온도 및 반응탑의 효율을 결정하기 위하여, 흡수층과 촉매층으로 구성된 분리반응탑을 모델링하고, 전산코드를 작성하였다. 이 전산코드의 결과는 실험치와 잘 일치하였으며, 최소반응단수를 갖는 설계온도는 8$0^{\circ}C$임이 밝혀졌다.

• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.82-83
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• 2010

환경시료 중 삼중수소의 방사능을 분석하기 위하여 전처리과정을 수행한다. 전처리의 주요 절차는 증류와 발광액의 첨가 그리고 약 24시간의 암실보관 등이다. 본 보고서에서는 각 전처리 과정이 방사능 측정결과에 미치는 영향을 평가하고 전처리과정에서 피할 수 없는 오차와의 관계를 확인한 후 이를 통해 삼중수소의 방사능 세기에 따라 전처리과정의 상대적 중요도를 확인하고자 한다. 이 과정을 통해 전처리가 꼭 필요한 경우와 그렇지 않은 경우를 구분할 수 있는 방사능 세기의 문턱 값을 확인하고자 한다.

• Journal of Radiation Protection and Research
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• v.25 no.2
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• pp.75-80
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• 2000

The predicted results of INDAC code were compared with measured $^3H$ concentrations in air and pine-needle around the Wolsung site. The optimal sets of input data to INDAC were in addition selected by comparing the measured values with the predicted values of INDAC based on various conditions such as the release modes of effluents into the environment, the classification of wind classes, and the consideration of terrain. The predicted $^3H$ concentrations in air and pine-needle were shown to have good agreement with measured values, although there are some limitations such as uncertainties in measured values, complex topology around the site, and the land-sea breeze effects. The assumption on the $^3H$ behavior in vegetables or plants that the ratio of $^3H$ concentration in plant water to $^3H$ concentration in atmospheric water is 1/2 was shown to be conservative in terms of the audit calculation performed by the regulator. It was also found that data sets based on mixed mode and no terrain data were not appropriate for the audit calculation ensuring the compliance with regulations. Thus, if the mixed mode is considered as the release mode of effluents into the environment, meteorological data measured at 58 m height and terrain data should be used to evaluate the atmospheric dispersion factor.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.379-380
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• 2009

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.913-917
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• 1995

인체내로 흡입된 삼중수소에 의한 영향을 평가하기 위한 기존의 내부피폭 평가 모델들을 검토하고, 이를 사용하여 body water와 OBT에 의한 선량을 계산하였다. 또한 이 모델들의 단점들을 도출하고, 이를 보안하기 위한 방안을 제시하였다.

• 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.30 no.1
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• pp.45-54
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• 2005

A dynamic compartment model was developed to appraise the level of the contamination of agricultural plants by accidentally released tritium from nuclear facility. The model consists of a set of inter-connected compartments representing atmosphere, soil and plant. In the model three categories of plant are considered: leafy vegetables, grain plants and tuber plants, of which each is modeled separately to account for the different transport pathways of tritium. The predictive accuracy of the model was tested through the analysis of the tritium exposure experiments for rice-plants. The predicted TFWT(tissue free water tritium) concentration of the rice ear at harvest was greatly affected by the absolute humidity of air, the ratio of root uptake, and the rate of rainfall, while its OBT(organically bound tritium) concentration the stowing period of the ear, the absolute humidity of air and the content of hydrogen in the organic phase. There was a good agreement between the model prediction and the experimental results lot the OBT concentration of the ear.

• 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.