• Journal of Korean Neurosurgical Society
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• 제43권3호
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• pp.159-161
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• 2008

A cerebrospinal fluid hydrothorax is a very rare complication following ventriculoperitoneal (VP) shunt and usually reported in children. We report a case of 47-year-old woman who developed massive hydrothorax and respiratory distress following intrathoracic migration of distal shunt catheter. After the confirmation of catheter in thoracic cavity using radionuclide shuntogram, the patient was successfully treated with laparoscopic shunt catheter reposition.

• Nuclear Engineering and Technology
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• 제26권3호
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• pp.401-410
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• 1994

실험실 규모의 인공균열 추적자 이동실험을 통해 지하매질의 단일균열을 위한 핵종이동 모델중 수리 분산확산모델 및 국부통로확산모델의 타당성이 연구되었다. 사용된 추적자는 비수착성으로 알려진 우라닌과 소디움 리그노설포네이트 이었으며 적용유량은 0.4에서 1.5cc /min의 범위였다. 최적화법으로 모델들의 관련 매개변수들을 구하였으며 모델과 실험결과를 비교하였다. 실험에서 우라닌은 암석내로의 확산이 중요한 인자임을 보여주었고, 두 물질 모두 균열 표면에서의 수착은 중요하게 작용하지 않았다. 두 모델의 암석 확산을 나타내는 매개변수값들은 서로 잘 일치하였다. 모사결과에 따르면 유량변화시 두 모델은 정량적으로 같은 결과를 주었으나, 균열길이는 다른 크기로 두 모델에 영향을 주었다. 즉, 균열길이가 커짐에 따라 국부통로화산모델의 파과곡선 퍼짐성 (dispersivity)이 수리분산화산모델의 파과곡선 퍼짐성보다 증가하였다. 실험과 모델들의 일치는 위 두모델들이 단일 균열 시스템을 해석하는데 매우 유용함을 입증하였다.

• Journal of Radiation Protection and Research
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• 제35권1호
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• pp.6-11
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• 2010

Embodying the safety of radioactive waste disposal requires the relevant safety criteria and the corresponding stylized methods to demonstrate its compliance with the criteria. This paper proposes a conceptual model of risk-based safety evaluation for integrating complex potential radiation exposure situations in radioactive waste disposal. For demonstrating compliance with a risk constraint, the approach deals with important exposure scenarios from the viewpoint of the receptor to estimate the resulting risk. For respective exposure situations, it considers the occurrence probabilities of the relevant exposure scenarios as their probability of giving rise to doses to estimate the total risk to a representative person by aggregating the respective risks. In this model, an exposure scenario is simply constructed with three components:radionuclide release, radionuclide migration and environment contamination, and interaction between the contaminated media and the receptor. A set of exposure scenarios and the representative person are established from reasonable combinations of the components, based on a balance of their occurrence probabilities and the consequences. In addition, the probability of an exposure scenario is estimated on the assumption that the initiating external factors influence release mechanisms and transport pathways, and its effect on the interaction between the environment and the receptor may be covered in terms of the representative person. This integrated approach enables a systematic risk assessment for complex exposure situations of radioactive waste disposal and facilitates the evaluation of compliance with risk constraints.

• 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.

• 한국토양비료학회지
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• 제19권3호
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• pp.251-268
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• 1986

Selecting a site for the safe disposal of radioactive waste requires the evaluation of a wide range of geologic, mineralogic, hydrologic, and physicochemical properties. Although highly diverse, these properties are in fact interrelated. Site requirements are also diverse because they are influenced by the nature of the radionuclides in the waste, for example, their half-lives, specific energy, and chemistry. A fundamental consideration in site selection is the mineralogy of the host rock, and one of the most ubiquitous mineral groups is clay minerals. Clays and clay minerals as in situ lithologic components and engineered barriers may playa significant role in retarding the migration of radionuclides. Their high sorptivity, longevity (stability), low permeability, and other physical factors should make them a very effective retainer of most radionuclides in nuclear wastes. There are, however, some unanswered questions. For example, how will their longevity and physicochemical properties be influenced by such factors as radionuclide concentration, radiation intensity, elevated temperatures, changes in redox condition, pH, and formation fluids for extended periods of time? Understanding of mechanisms affecting clay mineral-radionuclide interactions under prevailing geochemical conditions is important; however, the utilization of experimental geochemical information related to physicochemical properties of clays and clay-bearing materials with geohydrologic models presents a uniquely challenging problem in that many assessments have to be based on model predictions rather than on experiments. These are high-priority research investigations that need to be addressed before complete reliance for disposal area performance is made on clays and clay minerals.

• 방사성폐기물학회지
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• 제20권4호
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• pp.399-410
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• 2022

The solubility and species distribution of radionuclides in groundwater are essential data for the safety assessment of deep underground spent nuclear fuel (SNF) disposal systems. Americium is a major radionuclide responsible for the long-term radiotoxicity of SNF. In this study, the solubility of americium compounds was evaluated in synthetic groundwater (SynDB3), simulating groundwater from the DB3 site of the KAERI Underground Research Tunnel. Geochemical modeling was performed using the ThermoChimie_11a thermochemical database. Concentration of dissolved Am(III) in Syn-DB3 in the pH range of 6.4-10.5 was experimentally measured under over-saturation conditions by liquid scintillation counting over 70 d. The absorption spectra recorded for the same period suggest that Am(III) colloidal particles formed initially followed by rapid precipitation within 2 d. In the pH range of 7.5-10.5, the concentration of dissolved Am(III) converged to approximately 2×10^-7 M over 70 d, which is comparable to that of the amorphous AmCO₃OH(am) according to the modeling results. As the samples were aged for 70 d, a slow equilibrium process occurred between the solid and solution phases. There was no indication of transformation of the amorphous phase into the crystalline phase during the observation period.

• 대한핵의학회지
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• 제24권2호
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• pp.279-285
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• 1990

Simultaneous presence of ascites and pleural effusion has been documented in patients with cirrhosis of the liver, renal disease, Meigs' syndrome and in patients undergoing peritoneal dialysis. Mechanisms proposed in the formation of pleural effusion in most of the above diseases are lymphatic drainage and diaphragmatic defect. But sometimes, hepatic hydrothoraxes in the absence of clinical ascites and pleural effusion secondary to pulmonary or cardiac disease are noted. It is not always possible to differentiate between pleural effusion caused by transdiaphragmatic migration of ascites and by other causes based soly on biochemical analysis. Authors performed radionuclide scintigraphy after intraperitoneal administration of $^{99m}Tc-labeled$ colloid in 23 patients with both ascites and pleural effusion in order to discriminate causative mechanisms responsible for pleural effusion. Scintigraphy demonstrated the transdiaphragmatic flow of fluid from the peritoneum to pleural cavities in 13 patients correctly. In contrast, in 5 patients with pleural effusion secondary to pulmonary, pleural and cardiac diseases, radiotracers fail to traverse the diaphragm and localize in the pleural space. Ascites draining to mediastinal lymph nodes and blocked passage of lymphatic drainage were also clarified, additionaly. Conclusively, radionuclide peritoneal scintigraphy is an accurate, rapid and easy diagnostic tool in patients with both ascites and pleural effusion. It enables the causes of pleural effusion to be elucidated, as well as providing valuable information required when determining the appropriate therapy.

• 방사성폐기물학회지
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• 제9권2호
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• pp.99-105
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• 2011

중저준위 방사성폐기물 처분장의 안전성 평가를 위하여 지하 사일로와 그 주변의 굴착손상영 역 (EDZ) 및 단열암반을 고려한 지하수유동해석과 핵종이동해석의 통합모델을 개발하였다. 사일로를 다중방벽개념으로 고려하여 사일로를 구성하는 3개의 특성지역 (waste, buffer, concrete)으로 구분하여 해석하였고, EDZ는 사일로 주변과 건설운영 터널 주변의 손상영역을 고려하였다. 단열암반의 불균일성은 분리단열 (discrete fractures)로 부터 해석된 불균일한 지하수 유속계로 도출하였고, 그 결과를 핵종의 이동경로를 모사하는데 사용하였다. 현 모델은 핵종누출에 따른 사일로 배치의 최적화와 안전성의 정량화를 도출하는데 사용가능하다.

• Nuclear Engineering and Technology
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• 제27권2호
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• pp.176-188
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• 1995

지하처분된 방사성핵종의 이동 해석방식으로서 입자추적법을 도입하였다. 입자추적법은 암반균열대와 같은 흐름장이 불균일하고 복잡할 때 물질이동을 모사할 수 있는 방법이다. 암반층에서 방사성핵종은 주로 암반사이에 발달한 균열을 따라 이동하는데, 초기연구자들은 균열틈을 평행판 사이의 간격으로 가정하였으나, 실제 균열은 이보다 복잡다양해서 실제 물질 이동과는 상당한 오차가 존재하였다. 이 논문에서는 이를 극복하기 위해 가변균열폭 국부통로모형을 도입하여, 균열대 내부는 2차원적인 균열폭의 분포를 가지며, 핵종은 균열내에서 상대적으로 큰 균열폭을 따라 이동이 주로 일어나는 국부이동이 라는 점을 제시하였다. 또한 개발한 이동모델의 타당성 입증차원에서 자연균열을 가진 화강암을 사용하여 방사성 핵종 이동 실험을 수행하였다. 추적자로서 지하수와 같은 이동특성을 가진 삼중수소와 요오드를 사용하였다. 화강암 균열대 특성을 파악하기 위해 균열이 있는 윗 암석면에 11개의 시추공을뚫고 수리전도 시험을 수행하였다. 실험자료와 전산모사치를 비교해 본 결과, 가변균열폭국부통로 개념에 물질이동모델로 입자추적법을 결합한 모델이 암반균열에서 핵종이동 해석방법으로 유용하였다. 또한 핵종은 균열 내에서 상대 적으로 큰 국부통로를 따라 주로 이동하며, 이동방향과 직각인 암반매질내로 확산도 상당한 비율로 일어났다.

• Journal of Radiation Protection and Research
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• 제16권2호
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• pp.27-39
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• 1991

압축된 국산벤토나이트에서 Sr-85, Cs-237, Co-60 및 Am-241의 확산연구를 수행하였다. 본 실험에서는 원통형으로 압축된 벤토나이트 시료의 중앙부에서 축 방향으로 방사성핵종의 확산이동이 이루어지도록 하여 각 방사성핵종의 확산계수를 측정하였다 그리고 벤토나이트의 열처리 온도와 압축밀도가 확산에 미치는 영향 등을 분석하였다. Sr-85, Cs-137, Co-60 및 Am-241의 겉보기 확산계수는 각각 $1.07{\times}10^{-11},\;6.705{\times}10^{-13},\;1.226{\times}10^{-13},\;1.310{\times}10^{-14},\;m^2/sec$로 측정되었다. 그리고 시료의 압축 밀도를 $1.8g/cm^2$에서 $2.0g/cm^2$으로 증가시켰을 때, Cs-137의 확산계수는 약 1/4로 감소되어 나타났다. 반면, 열처리된 벤토나이트의 경우에는 확산계수가 크게 변하지 많았는데, 이는 $150^{\circ}C$ 이하의 온도에서는 국산 벤토나이트가 방사성핵종의 이동을 지연시킬 수 있는 화학적 방벽으로서 사용할 수 있다는 가능성을 보여준 것이라 생각된다. 그리고 음이온 Cl-36의 화산계수를 이용하여 도출한 각 방사성핵종의 공극확산계수와 표면확산계수를 측정한 겉보기확산계수와 비교해 볼 때, 전체 방사성 핵종의 확산이동에 있어서 표면확산이동이 지배적인 것으로 나타났다.