• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.247-247
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• 2004

가압 중수로형 원자력발전소에서는 원자로의 감속재 및 냉각재로 사용하는 중수(heavy water)로 인한 삼중수소(tritium)의 생성이 전체 방사선 준위 상승의 가장 중요한 원인이 되고 있다. 따라서 4기의 중수로가 운전 중인 우리나라에서도 월성원자력 발전소에 삼중수소 제거 설비(Tritium Removal Facility)가 건설 중에 있다. 이 시설로부터 99% 이상의 순도인 삼중수소가 회수되며, 회수된 삼중수소는 장기적인 저장을 위하여 안전하게 포장되어야 한다.(중략)

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.295-300
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• 1997

백금족 원소인 Rhodium 과 Palladium 담지 SDBC 고분자촉매를 제조하여 삼중수소 분리반응 특성을 실험하였다. 수중에서도 고활성을 유지하는 소수성촉매 제조를 위하여 고수율의 벌크중합법에 의한 SDBC 고분자담체를 합성하였다. 삼중수소 분리반응실험은 수소유속과 반응온도를 촉매물질에 따라 변화 시켜서 반응효율을 측정함으로써 수행하였다. 실험결과 Rhodium-SDBC 와 Palladium-SDBC 공히 삼중수소 분리반응에 활성이 있는 것으로 나타났으며, 특히 Rhodium은 유망한 백금대체 촉매물질로 개발될 수 있음이 밝혀졌다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.484-490
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• 2003

The amount of the tritium released from Wolsong units during the WTRF operation is predicted. The profiles of tritium concentration in moderators and PHTs as variation of WTRF service allotment for each Wolsong unit are calculated, and the tritium releases are obtained from these tritium concentration profiles. The tritium concentration in moderator will be decreased down under 10 Ci/kg in 2013 and the yearly tritium release will be reduced below 25% of WTRF start year.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.10a
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• pp.415-416
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• 2010

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.222-223
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• 2009

• Journal of Radiation Protection and Research
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• v.36 no.2
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• pp.99-106
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• 2011

Tritium is the one of the most important radionuclide for workers in nuclear power plants (NPPs) and the public, from the dosimetric point of view. Humans are likely to have internal radiation exposure by tritium inhalation. Radiation exposure by tritium accounts for approximately 7% and 60~90% of the total radiation exposure of NPP workers and the public during normal operation, respectively. Thus, many researches have been conducted to estimate the internal dose by tritium precisely in the world. In terms of tritium dosimetry, this paper provides the current status of research for tritium metabolism and dosimetry.

• 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 $7.85{\pm}0.46\;TU$.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.511-511
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• 2012

핵 융합로는 고밀도, 고에너지 플라즈마에 지속적으로 노출되며 고열부하 및 중성자, 플라즈마 이온에 의한 물성변화에 대한 다양한 핵 융합로 구축 재질의 실험데이터가 요구된다. 특히 핵 융합 반응의 핵심연료인 삼중수소의 재질별 누설거동 특성은 삼중수소의 블랑켓에서의 증식율, 열 교환기 및 공급과 회수과정에서의 손실율, 저장, 취급 및 차폐 등의 계산에 활용되므로 핵 융합로의 안전성과 경제성 확보 측면에서 매우 중요하다. 따라서 핵 융합로 구축 재질 선정시 삼중수소의 누설거동 특성은 반드시 고려되어야 한다. 본 연구는 삼중수소 누설거동 특성 해석을 위한 기초실험으로, 수소동위원소를 사용하는 누설거동실험 장치를 설계 제작하여 누설 거동실험을 수행하였다. 누설 가스로는 수소를 사용하였고, 시편은 스테인레스 스틸(SUS-304)을 사용하였으며, 시편의 가열온도는 500, 600, 700, $800^{\circ}C$에서 각각 수소누설거동 실험을 실시하였다. 수소에 대한 SUS-304 재질의 permeability, diffusivity, solubility에 대한 실험 결과를 발표하고자 한다.

• Analytical Science and Technology
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• v.17 no.3
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• pp.251-262
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• 2004

It is for the purpose of investigating the tritium distribution in the leachates, the raw and treated leachates and the condensates of the methane gas, which have occurred from domestic solid waste landfills. Also it aims to measure the tritium distribution level on the colloid size of the leachates, the raw and treated leachates. It was found that the major inorganic contaminants of the leachates were Na, K, Ca, Mg, $NH{_4}^+$-N and $Cl^-$. The mean tritium level of the raw leachates of the investigated 13 landfill sites for 6 months was 17 ~ 1196 TU. It corresponded to a several scores or hundreds of magnitude higher value than that of the normal environmental sample level except for two landfill sites. Also such a high concentration of the tritium was found in the treated leachates and methane gas condensates as well. Nevertheless it is important to emphasize that the tritium level which was found in this research is about 100 times lower than the tritium limit for the drinking water quality. And most of the tritium existed in the dissolved colloid of the leachate of which the colloid size is below $0.45{\mu}m$. Also, according to the tritium analysis results of the leachates after filtration with $0.45{\mu}m$ membrane filter for some landfills, it is likely that some tritium of the leachate would be distributed in a colloid size over $0.45{\mu}m$. In general the relationship between the tritium and other contaminants in the raw leachate was low, but it was relatively high between the tritium and TOC. However, the tritium content in the leachate had no meaningful relationship with the scale, hydrological characteristics and age of the landfill.

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.134-135
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• 2009