• Journal of Radiation Protection and Research
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• v.28 no.1
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• pp.75-78
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• 2003

The organically bound tritium(OBT) concentrations of the marine organisms(seaweed and shellfish) around Wolsung nuclear power plants were measured. The OBT concentrations of seaweeds were in the range of $0.372{\sim}2.72$ Bq/kg-fresh. The OBT concentrations of shellfish were in the range of $0.239{\sim}2.02$ Bq/kg-fresh. The internal dose due to the OBT concentration of seaweed was estimated as $3.4{\times}10^{-7}$ mSv/year.

• Journal of Radiation Protection and Research
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• v.23 no.1
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• pp.25-32
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• 1998

Tritium is released into the environment as various form but HTO is most relevant to the incorporation of tritium into living organisms and to the formation of OBT. Tritiated compounds may be transported to humans via several tropic levels. Retention times of organically bound tritium in organisms are considerably longer than those of tritiated water, which has significant consequences on exposure dose estimation. It is rather difficult to predict the amount of OBT produced by the photosynthetic process of plants because it may be influenced by a multitude of environmental factors and plant parameters. Tritiated organic matters are classified as the exchangeable or nonexchangeable bound tritium according to the bound form. After short term HTO exposure in plants, the formation and uptake of OBT were evaluated.

• Journal of Sensor Science and Technology
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• v.9 no.3
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• pp.153-162
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• 2000

Triple points of high purity materials have been used to calibrate primarily the capsule-type platinum resistance thermometer (PRT) in the temperature range of the triple point of equilibrium hydrogen (13.8033 K) and water (273.16 K). In this work, triple points of Ne, $O_2$, Ar, Hg and $H_2O$ except for the triple point of equilibrium hydrogen were realized to establish the International Temperature Scale of 1990 (ITS-90). At each fixed point, two capsule-type PRTs, which were selected for the international comparison, were tested two times. The combined uncertainties of the realization of each triple point were calculated considering the type A and type B evaluation. In Korea Research Institute of Standards and Science, the combined standard uncertainties of the defining triple Points by the ITS-90 were estimated to about 0.18 mK for Ne, 0.14 mK for $O_2$, 0.14 mK for Ar, 0.24 mK for Hg and 0.11 mK for $H_2O$, respectively.

• Nuclear Engineering and Technology
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• v.27 no.4
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• pp.626-634
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• 1995

소수성 고운자촉매는 중수형 원자력발전소의 감속재 및 냉각재로 사용되는 중수의 제조, 그리고 발전소의 가동에 따라 중수중에 축적되는 삼중수소의 제거공정 둥에 이용된다. 여러 소수성 담체중 하나인 소수성 고분자담체를 제조하기 위하여 스티렌-디비닐벤젠의 제조 특성을 실험하였다. 제조된 담체에 백금 금속을 담지시켜 촉매를 완성한 후 삼중수소제거 실증실험을 통하여 촉매성능을 확인하였다. 스티렌-디비닐벤젠 고분자담체의 제조시 담체의 기공 특성 및 비표면적에 대한 용매의 영향을 실험하였다. 또한 용매비를 변화시킨 경우에는 solvating power 값을 계산하여 거시기공 형태의 담체 형성기준을 정하였고 여기에 따른 기공 특성 및 비표면적 변화를 부인하였다. 담체의 제조 후 후처리 방법을 변화시켜 기공 특성 및 비표면적 변화를 확인하였고, 이의 결과를 통하여 적절한 후처리 방법을 정하였다. 담체의 입자크기를 조절하기 위해 중합반응 과정중의 교반속도를 변화시켜 담체의 크기 변화를 실험하였다. 제조된 담체에 백금 금속을 담지시켜 촉매를 완성한 후 삼중수소제거 반응실험을 통해 촉매의 활성을 확인하였다.

• Korean Chemical Engineering Research
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• v.58 no.4
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• pp.596-603
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• 2020

In this study, a mathematical model for optimal operation of the fusion fuel cycle is developed based on scheduling approach. The fusion fuel cycle consists of a system for storing and supplying deuterium and tritium, and receiving and separating process after the fusion reaction. Except that tritium is a radioactive material, most of these processes consist of catalytic reactions and separation process. For these reasons, it is possible to apply scheduling approach which is also widely utilized to chemical plants to derive the optimal operating scenarios. The developed model determined the optimal regeneration cycle to minimize the amount of tritium inside the vacuum pumps. Based on the characteristics of various device in the fusion reactor, the optimal tritium plant operation scenario is evaluated. The formulated model was applied to the actual tokamak scenario and utilized to analyze the fuel flow and balance of ITER fuel cycle.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.125-126
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.463-464
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• 2012

• Applied Chemistry for Engineering
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• v.9 no.1
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• pp.121-128
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• 1998

In fields of operating or handling a hydrogen isotope facility, and of the technology for nuclear fusion source management, gas chromatography has been used as one of the practical techniques lot separation and enrichment of hydrogen isotopic gases including tritium. Chromatographic separation experiments of the hydrogen isotope mixture (hydrogen, deuterium and tritium) were carried out by use of a commercially available gas chromatograph. An aliquot of gas sample was injected by a specially designed vacuum sampler into the stream of inert carrier gas which went through the separation column under liquid nitrogen temperature. The complete separation of hydrogen isotopic molecules was observed with an alumina adsorbent partially deactivated by coating with 10% manganese chlorine. In addition, fairly good separation conditions were obtained without any appearance of nuclear spin isomers with shorter retention time, which would be available for the practical applications of the hydrogen isotope separation and enrichment.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.401.1-401
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• 2001

• Proceedings of the Korea Air Pollution Research Association Conference
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• 1995.10a
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• pp.95-96
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• 1995