• Journal of Radiation Protection and Research
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• 제34권4호
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• pp.184-189
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• 2009

중수로원전의 방사선작업종사자는 방사선작업 종료 후에 뇨시료를 제출하여 공기중 삼중수소의 섭취에 따른 내부피폭 선량을 평가하고 있다. 이 경우 종사자가 제출한 뇨시료는 삼중수소가 체내에서 평형에 도달한 대표시료(Representative sample)라는 전제를 필요로 한다. 국제방사선방호위원회(ICRP)의 간행물과 삼중수소의 인체평형에 대한 캐나다의 실험결과에 의하면 체내로 유입된 삼중수소는 약 2-3시간 후에 평형에 도달한다고 기술하고 있다. 그런데 원전에서는 계획예방정비기간 동안 일시에 많은 작업이 진행되고 빈번한 종사자의 출입으로, 방사선작업 종료 후 제출하는 뇨시료는 섭취 후 평형에 도달하는 약 2시간 경과 이전에 제출하거나, 지연하여 제출하는 경우가 발생할 수 있다. 따라서 이 논문에서는 방사선작업 종료 후 종사자가 제출하는 시간대별 뇨시료 중의 삼중수소 농도를 측정하였고, 이를 근거로 체내 삼중수소의 농도에 대한 변화추이와 선량평가에 미치는 영향을 분석하였다. 그 결과 종사자의 뇨시료는 대부분 삼중수소 섭취 후 2시간 정도에 신체 내에서 평형에 도달하는 것으로 확인되었다.

• 한국지구물리탐사학회:학술대회논문집
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• 한국지구물리탐사학회 2003년도 Proceedings of the international symposium on the fusion technology
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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.

• 분석과학
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• 제23권2호
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• pp.161-164
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• 2010

지하수 연구를 위한 추적자로 삼중수소를 이용하기 위해서는 강우중 삼중수소 양을 알아야 하므로 본 연구에서는 2007년부터 2009년까지 대전에서 매 월 강우를 채집하여 삼중수소 함량변화를 분석하였다. 분석 결과 강우중의 삼중수소 양은 최소 4.2 TU부터 최대 18.6 TU의 변화를 보였으며 여름과 겨울에 삼중수소의 양이 감소하고 봄과 가을에 그 양이 증가하는 경향을 나타내었다. 강우중의 평균 삼중수소 양을 강우량과 연관한 가중평균을 구한 결과 $7.85{\pm}0.46\;TU$를 나타내었다.

• 대한화학회지
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• 제40권6호
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• pp.436-444
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• 1996

전주근교 약수터 15개 지점에 대하여 그들의 수질특성을 1993년 7월부터 1994년 5월까지 1년 동안에 걸쳐 물속의 삼중수소를 기준으로 삼중수소와 TDS, 삼중수소와 전도도, 삼중수소와 $Cl^-$, 그리고 삼중수소와 총경도의 관계로부터 평가하였다. 이들 약수터 물은 빗물과 유사한 단물, 유동기간이 짧으며 흙층을 통과한 센물, 유동기간이 길고 암반층을 유동한 약한센물, 유동기간이 길고 암반층을 유동한 단물의 특징적 그룹으로 나눌 수 있으며 대부분 빗물과 유사한 물로 해석되었다. Hashimoto의 Mineral Balance Index에 의하면, J-4용천수만 맛있고 건강한 물로 평가되었다.

• 방사선산업학회지
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• 제2권3호
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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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• 제52권2호
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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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(4)
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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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• 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.

• 한국수소및신에너지학회논문집
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• 제23권1호
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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.

• 한국수소및신에너지학회논문집
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• 제24권2호
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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.