• Journal of Radiation Protection and Research
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• 제17권2호
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• pp.49-59
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• 1992

이온 또는 착화된 상태의 방사성핵종의 이동에 대한 착화제의 영향을 조사하기 위하여 새로운 모델이 제시되었다. 착화된 방사성핵종의 이동거동은 착화제와 착화된 방사성핵종의 열화를 포함하는 대류-확산 이동방정식에 의해 해석되었다. 이 수학적 모델은 해석적인 방법 에 의해 구해졌으며 지연요소를 조사함으로써 분석되었다. 계산결과들은 감소된 지연요소에 의해 착화된 방사성핵종의 이동속도가 이온형태의 방사성핵종보다 매우 빠름을 보여주었다. 따라서 원자력발전소로부터의 착화제의 발생과 환경으로의 유출을 감소시킬 수 있는 새로운 구제책이 필요하다고 하겠다.

• Nuclear Engineering and Technology
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• 제42권5호
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• pp.562-567
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• 2010

A One-Dimensional Water Flow and Contaminant Transport in Unsaturated Zone (FTUNS) code has been developed in order to interpret radionuclide migration in an unsaturated zone. The pore-size distribution index (n) and the inverse of the air-entry value ($\alpha$) for an unsaturated zone were measured by KS M ISO 11275 method. The hydraulic parameters of the unsaturated soil are investigated by using soil from around a nuclear facility in Korea. The effect of hydraulic parameters on radionuclide migration in an unsaturated zone has been analyzed. The higher the value of the n-factor, the more the cobalt concentration was condensed. The larger the value of $\alpha$-factor, the faster the migration of cobalt was and the more aggregative the cobalt concentration was. Also, it was found that an effect on contaminant migration due to the pore-size distribution index (n) and the inverse of the air-entry value ($\alpha$) was minute. Meanwhile, migrations of cobalt and cesium are in inverse proportion to the Freundich isotherm coefficient. That is to say, the migration velocity of cobalt was about 8.35 times that of cesium. It was conclusively demonstrated that the Freundich isotherm coefficient was the most important factor for contaminant migration.

• 방사성폐기물학회지
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• 제7권4호
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• pp.243-253
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• 2009

본 연구에서는 KURT (KAERI 지하처분연구시설)를 포함한 지하연구시설에서 핵종 및 콜로이드 이동에 대한 연구현황을 조사하였다. 화강암과 같은 결정질 암반층에 건설된 해외 지하연구시설들을 간략하게 소개하고 비교하였다. 특히 Grimsel Test Site (GTS)와 $\ddot{A}$sp$\ddot{o}$ Hard Rock Laboratory에서의 핵종 및 콜로이드 이동연구에 대한 주요 국제공동연구의 연구항목 및 내용, 진행중인 연구 프로젝트, 연구계획 등에 대해 조사하였다.

• Nuclear Engineering and Technology
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• 제40권7호
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• pp.593-606
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• 2008

In this study, data on radionuclide migration and retardation processes in the engineered and natural barriers of High-Level Radioactive Waste (HLW) repository have been reviewed and compiled for use in the performance assessment of a HLW disposal system in Korea. The status of the database on radionuclide migration and retardation that is being developed in Korea is investigated and summarized in this study. The solubilities of major actinides such as D, Th, Am, Np, and Pu both in Korean bentonite porewater and in deep Korean groundwater are calculated by using the geochemical code PHREEQC (Ver. 2.0) based on the KAERI-TDB(Korea Atomic Energy Research Institute-Thermochemical Database), which is under development. Databases for the diffusion coefficients ($D^b_e$ values) and distribution coefficients ($K^b_d$ values) of some radionuclides in the compacted Korean Ca-bentonite are developed based upon domestic experimental results. Databases for the rock matrix diffusion coefficients ($D^r_e$ values) and distribution coefficients ($K^r_d$ values) of some radionuclides for Korean granite rock and deep groundwater are also developed based upon domestic experimental results. Finally, data related to colloids such as the characteristics of natural groundwater colloids and the pseudo-colloid formation constants ($K_{pc}$ values) are provided for the consideration of colloid effects in the performance assessment.

• 방사성폐기물학회지
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• 제20권4호
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• pp.455-468
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• 2022

Colloid Formation and Migration (CFM) project is being carried out within the Grimsel Test Site (GTS) Phase Ⅵ. Since 2008, the Korea Atomic Energy Research Institute (KAERI) has joined CFM to investigate the behavior of colloid-facilitated radionuclide transport in a generic Underground Research Laboratory (URL). The CFM project includes a long-term in-situ test (LIT) and an in-rock bentonite erosion test (i-BET) to assess the in-situ colloid-facilitated radionuclide transport through the bentonite erosion in the natural flow field. In the LIT experiment, radionuclide-containing compacted bentonite was equipped with a triple-packer system and then positioned at the borehole in the shear zone. It was observed that colloid transport was limited owing to the low swelling pressure and low hydraulic conductivity. Therefore, a postmortem analysis is being conducted to estimate the partial migration and diffusion of radionuclides. The i-BET experiment, that focuses more on bentonite erosion, was newly designed to assess colloid formation in another flow field. The i-BET experiment started with the placement of compacted bentonite rings in the double-packer system, and the hydraulic parameters and bentonite erosion have been monitored since December 2018.

• 방사성폐기물학회지
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• 제19권1호
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• pp.113-121
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• 2021

A safety assessment of radioactive waste repositories is a mandatory requirement process because there are possible radiological hazards owing to radionuclide migration from radioactive waste to the biosphere. For a reliable safety assessment, it is important to establish a parameter database that reflects the site-specific characteristics of the disposal facility and repository site. From this perspective, solubility, a major geochemical parameter, has been chosen as an important parameter for modeling the migration behavior of radionuclides. The solubilities were derived for Am, Ni, Tc, and U, which were major radionuclides in this study, and on-site groundwater data reflecting the operational conditions of the Gyeongju low and intermediate level radioactive waste (LILW) repository were applied to reflect the site-specific characteristics. The radiation dose was derived by applying the solubility and radionuclide inventory data to the RESRAD-OFFSITE code, and sensitivity analysis of the dose according to the solubility variation was performed. As a result, owing to the low amount of radionuclide inventory, the dose variation was insignificant. The derived solubility can be used as the main input data for the safety assessment of the Gyeongju LILW repository in the future.

• 대한핵의학회지
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• 제32권6호
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• pp.482-489
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• 1998

목적: 방사성 동위원소 뇌조조영술은 자발성 두 개 내 저압환자의 체위성 두통과 저뇌척수압의 병태생리를 이해하는데 도움을 줄 수 있다. 저자들은 이 질환의 방사성 동위원소 뇌조조영술의 특징적인 소견을 알아보고자 하였다. 대상 및 방법: 자발성 두개내 저압으로 진단되어 방사성 동위원소 뇌조조영술을 시행한 15명을 대상으로 하였다. 뇌조조영술은 Tc-99m DTPA 111-222 MBq를 요추천자를 통해 지주막하강에 투여한 후 감마카메라로 30분부터 2시간 이내에 방광을 포함한 요추부와 경흉추부의 전면상과 측면상을 얻었고, 4, 6, 24시간에 두부와 경흉추부의 전면상과 측면상을 얻었다. 방광 내 방사성 추적자의 조기 배설유무, 척수강 내 방사성의 이동속도, 연조직 섭취정도, 그리고 대뇌궁융부로의 이동 지연 등을 분석하였다. 결과: 방사성 동위원소 뇌조조영술 소견은 대뇌궁융부로의 방사성 추적자의 이동지연(14/15), 연조직의 섭취증가(11/15), 방광 내 방사성 추적자의 조기 출현(13/13) 등이 있었고 뇌척수액의 누출을 시사하는 척수경막강 주위의 방사성 추적자의 국소 집적도 4예에서 있었다. 결론: 방사성 추적자의 이동 지연과 연조직의 섭취증가 및 방광 내 방사성 추적자의 조기 출현 등이 특징적으로 관찰되었고, 이러한 뇌조조영술 소견은 자발성 두개 내 저압의 주된 병태생리가 뇌척수액의 누출임을 시사하는 것으로 판단되었으며, 방사성 추적자 이동의 역동적 측면을 잘 평가하기 위해서는 방광과 연조직을 포함한 30분 영상과 다발적인 연속영상을 획득하는 것이 필요하다고 생각된다.

• 대한핵의학회지
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• 제33권2호
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• pp.184-188
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• 1999

Although cerebrospinal fluid leakage is suggested as one of the causes of spontaneous intracranial hypotension, only a few cases with direct evidence of cerebrospinal fluid leakage on radionuclide cisternography have been reported in the literature. Indirect evidences of cerebrospinal fluid leakage such as early visualization of the soft tissue and bladder or delayed migration of radiotracer have been observed in most patients with spontaneous intracranial hypotension. We report a case of spontaneous intracranial hypotension in which cerebrospinal fluid leakage was directly demonstrated by early dynamic imaging of spine on radionuclide cisternography. We suggest that early dynamic imaging of spine is an important adjunctive procedure in detecting cerebrospinal fluid leakage in patients with spontaneous intracranial hypotension.

• 방사성폐기물학회지
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• 제20권4호
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• pp.371-382
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• 2022

Carbonates are inorganic ligands that are abundant in natural groundwater. They strongly influence radionuclide mobility by forming strong complexes, thereby increasing solubility and reducing soil absorption rates. We characterized the spectroscopic properties of Am(III)-carbonate species using UV-Vis absorption and time-resolved laser-induced fluorescence spectroscopy. The deconvoluted absorption spectra of aqueous Am(CO₃)₂^- and Am(CO₃)₃^3- species were identified at red-shifted positions with lower molar absorption coefficients compared to the absorption spectrum of aqua Am³⁺. The luminescence spectrum of Am(CO₃)₃^3- was red-shifted from 688 nm for Am³⁺ to 695 nm with enhanced intensity and an extended lifetime. Colloidal Am(III)-carbonate compounds exhibited absorption at approximately 506 nm but had non-luminescent properties. Slow formation of colloidal particles was monitored based on the absorption spectral changes over the sample aging time. The experimental results showed that the solubility of Am(III) in carbonate solutions was higher than the predicted values from the thermodynamic constants in OECD-NEA reviews. These results emphasize the importance of kinetic parameters as well as thermodynamic constants to predict radionuclide migration. The identified spectroscopic properties of Am(III)-carbonate species enable monitoring time-dependent species evolution in addition to determining the thermodynamics of Am(III) in carbonate systems.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.231-232
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• 2017