• 한국의학물리학회지:의학물리
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• 제5권1호
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• pp.75-85
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• 1994

2000년대에 진입하게 되면 월성원자력발전소에서는 4기의 가압중수로형 원자로가 상업발전을 하게 되어서 많은 양의 삼중수소($^{3}$H)가 필연적으로 주변환경에 누출될 것이다. 이러한 방사성 핵종은 삼중수소의 형태로 편재되어 있으면서도 지속성을 갖고 있어서 우리의 환경에 쉽게 분포된다. 삼중수소는 베타방사선량 계측과 보건위해 평가를 위해 독특한 과제를 제시하는 특성을 갖고 있어서 본 논문에서는 삼중수소에 관한 여러가지 문제들을 보건물리와 관련하여 특성과 원천, 신진대사와 선량계측, 미세선량계측, 방사생물, 위해평가, 환경 경로 및 순환 등의 견지에서 정리하였다.

• Ocean Science Journal
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• 제43권1호
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• pp.39-48
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• 2008

Tritium ($^3H$ or T) has been produced mostly by atmospheric nuclear weapon tests, and entered the ocean in the form of water (HTO). As tritium exists as water itself, it has been regarded as an ideal tool to study the transport of water masses. In April 2001 we collected water samples in the western Japan Basin (WJB) for tritium and helium measurement. The timely sampling provided direct evidence of the bottom water formation, resulting in the drastic increase in tritium concentration from 0.3 TU in 2000 to 0.67 TU in 2001. Considering that the new bottom waters were found mostly in the WJB, it implies that maximum 1% of the whole bottom layer below 2600 m should be replaced with the surface water during the severely cold winter 2000 2001. $^3H-^3He$ age, showing the elapsed time since the water left from the surface, can be used to calculate oxygen utilization rate by dividing AOU by the age. Under the condition of 90% oxygen saturation in the surface water, the integration of OUR in the water column below 200 m yields net oxygen consumption of 12 mol $(O_2)m^{-2}yr^{-1}$, which corresponds to the export production of $99\;g\;C\;m^{-2}yr^{-1}$. This estimate is comparable to a previous estimate based on satellite data and implies that the ratio of export to primary production(f-ratio) is as high as 0.5 in the WJB.

• 한국환경복원기술학회지
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• 제16권3호
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• pp.55-62
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• 2013

Generally, the radioactivity from NPP(Nuclear Power Plants) operation can be released below 3% of DRLs(Derived Release Limits) to environment. It was tried to understand which plant was efficient for absorbing radioactivity in this study. Pinus thunbergii Parl. and Viburnum awabuki K. KOCH were analyzed for radioisotope absorption. The samples were collected at three different locations depending on the distance from NPP at the vicinity 10km away, and 30km away. Gamma radionuclide was not detected from the samples, which means that the direct transition into the plant was not significant. Meanwhile, the very low level of radioactive tritium was detected in the samples. One remark was that every plant has different ability for tritium absorption. These results are expected to be applied to propagation and transplanting in radioactively contaminated area or reducing radioactivity in the soil and water near the plants.

• Nuclear Engineering and Technology
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• 제28권3호
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• pp.274-279
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• 1996

Diffusion coefficient is a critical parameter for predicting radiological source term(migration rate and flux of radionuclide) through given near field conditions in spent fuel or high level waste repository. The effect of exchangeable cation-$Na^+$ and $Ca^{2+} - on the diffusion of $I^- \;and^3H$ (as HTO) in compacted bentonite was examined using a through-diffusion method. Bentonite material used here was compacted to a density of 1.3 Mg/m$^3$, and Na-bentonite was saturated with a solution of 100 mol NaCl/m$^3$ and Ca-bentonite with 50 $mol\;CaCl_2$/m$^3$. The results show that effective diffusion coefficients are generally higher by a factor of two to five in Ca-than Na-clay. This is attributed to the larger particle size of Ca-compared to Na-bentonite; hence, Ca-bentonite has a greater proportion of relatively large pores, which make a greater contribution to mass transport than small pores. Although the nature of the exchangeable cation affects mass diffusion in compacted bentonite, the effect is small and not likely to influence performance assessment modeling of compacted bentonite-based barriers.

• 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.

• 방사선산업학회지
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• 제17권4호
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• pp.437-442
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• 2023

This study conducted a comparative analysis of dose evaluations for ingestion of animal products based on data from nuclear power plants in the Republic of Korea, using methodologies from the Republic of Korea, 'IAEA TRS-472', and 'CSA N288.1:14'. The research focused on tritium, the most significant constituent among the gaseous and liquid radioactive emissions. The combined evaluation of tritium, in the form of tritiated water (HTO) and organically bound tritium (OBT), yielded results of 1.143 μSv y^-1 for the Republic of Korea, 0.965μSv y^-1 for 'TRS-472', and 0.886μSv y^-1 for 'N288.1:14'. Despite the Republic of Korea's guidelines not considering OBT, the evaluation results for the Republic of Korea were higher compared to other methodologies. This discrepancy was attributed to the unique approach of not considering the moisture content per individual in the calculations of plant and feed concentration in the Republic of Korea and the simultaneous consideration of specific-activity model and transfer model. The study highlights the necessity of developing dose evaluation models tailored to regional characteristics and underscores the importance of including OBT in these evaluations.

• 한국운동역학회지
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• 제14권3호
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• pp.135-147
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• 2004

This study was conducted to investigate the technical factors of Lu Yu Fu vault actually performed by three men gymnasts participated in artistic gymnastics competition of 2003 summer Universiade in Daegu through the DLT method of three dimensional cinematography. To analyze these vaults, the instant events of Lu Yu Fu were set in the board touchdown(BTD), the board takeoff(BTO), the horse touchdown(HTD), the horse takeoff(HTO), the peak height(PH), the mat touchdown(MTD) respectively and the phases of that vault were set in the board contact(BC), the preflight(PRF), the horse contact(HC), the postflight(POF), the grounding on mat(GM) respectively After calculating the performance times, the CG displacement velocity, the kinetic energy impulse reaction force moment arm torque at the horse, the released angle piked angle addressed angle, the angular momentum angular velocity of whole body in x axis, and the horizontal displacement between the feet and CG, the following conclusions were reached. To perform the better Lu Yu Fu vault, a gymnast must have the large horizontal velocity of whole body with fast run-up, decrease the duration time and the horizontal vertical displacement of whole body in PRF, have the enough time to judge the correct magnitude and direction of force to brake or push the horse so as to lengthen the HC duration time at any cost. Also it is desirable to increase the horizontal vertical displacement of whole body in POF if possible, maintain the adequate piked position to decrease the angular velocity of whole body in x axis, prepare the grounding on mat previously and delay the release of the hand from the body to keep the angular momentum.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.361-367
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• 2004

원전 주변 주민들의 $^3H$ 및 $^14C$ 섭취선량을 평가하는데 필요한 농작물중 $^3H$ 와 $^14C$농도를 계산하기 위하여 국내 4개 원전 주변 10개 지역에서 채취한 채소 및 과일류의 수분, 수소 및 탄소함량을 분석하였다. 조사 대상 농작물은 2001~2002년 보건복지부 국민건강ㆍ영양 조사결과에 근거하여 결정하였고, 그것들의 섭취량 백분율을 식품가중치로 취하여 그룹 대푯값을 산출하였다. 원전 주변 농작물 시료들의 수분, 수소 및 탄소함량을 분석한 결과, 곡류는 현재 원전의 주민피폭선량 평가코드인 K-DOSE60에 적용중인 값과 유사하게 나타났다. 무 등의 근채류는 현행 ODCM의 채소류보다 3.5배정도 높은 수소함량을 보였고, 엽채류 및 과일류의 수분, 수소 및 탄소함량이 현행 ODCM과 비교하여 약 0.7~1.3배정도의 값을 보였다.

• 대한기계학회논문집A
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• 제35권8호
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• pp.835-846
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• 2011

최근 보편화 되고 있는 내측개방형절골술 시에 의도하지 않은 경골후방경사각의 변화로 인한 문제점들이 보고되었다. 이를 해결하기 위해 많은 연구들이 진행되어 왔지만 환자의 다양한 경골의 형상 및 절단면의 기울기에 적용될 수 있는 일반적 해석 모델은 아직 제안되지 못하고 있다. 따라서 본 논문에서는 일반적인 케이스에 적용할 수 있는 근위경골절골술의 해석 모델을 제안한다. 이를 위해 내반교정각만을 조정할 수 있는 가상경골축을 정의하고, 이를 통해 절단면과 경골개방축이 내반교정각에 주는 영향을 나타내는 수학적 모델을 제안하고, 기존의 수술적인 변수들간의 상관관계를 명확히 나타내었다. 또한 내반교정각과 경골후방경사각에 추가로, 새로운 각도인 경골뒤틀림각의 존재를 도입함으로써 수술 시 발생하는 모든 기하학적 변수들간의 관계를 완성된 형태로 표현하였다.

• 한국대기환경학회지
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• 제3권1호
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• pp.27-33
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• 1987

삼중수소 ($^{3}H$) 에 관한 환경 및 생물학상의 연구는 1950년대 중반부터 선진국에서 수행되오고 있다. 삼중소소에 대한 잠재적 노출의 경우 통상적 처리절차는 삼중수소의 신체부하량이라고 일컬어지는 이른바 신체내에 축적된 삼중수소의 양을 결정하기 위하여 삼중수소수로서 오줌속에 포함되는 삼중수소 방사능의 생리분석이다. 전신에 있어서 삼중수소의 최대허용신체부하량은 신체조직에 대하여 약 $30{\mu}Ci/{\ell}$ 이다. 생리분석에서 오줌속에 삼중수소를 검출하는데 가장 보편적인 조사준위(照射准尉)는 최대허용신체부하량의 1/10 이다. 이러한 생리분석 연구계획을 위해서는 소광보정(消光補正) 곡선을 그리는 것이 가장 우선적이다. 이것은 검뇨용 오줌의 색깔이 일정하지 않기 때문에 필요한 것이다. 이 경우에서 소광효과는 주로 오줌시료에 의한 섬광빛의 흡수에 기인된다. 소광보정곡선으로 판단된 공식은 통계적 근거에서 최소자승법에 의하여 Y (%) = 0.771 + 1.836 ${\tmes}10^{-4}$X(count)로 얻어졌다. 여기서 Y는 섬광계수 효율로서 약 12%에서 31% 범위의 값으로 나타났다. 본 논문에서는 삼중수소의 생물학적 반감기와 신체계통적으로 분포된 삼중수소에 적용되고 있는 정체(停滯) 공식에 관한 간략한 이론에 관하여 서술된다.