• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 춘계학술발표회논문집(2)
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• pp.769-774
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• 1995

In this study, a transport model was developed in order to analyze and predict the transport behaviors of radionuclides mediated by pseudo-colloid in the fractured rock media. It was resulted that the transport of Pu-239 was faster than Ni-63 because pseudo-colloid formation constant of Pu-239 was greater than that of Ni-63. Also, the effect of pseudo-colloid formation on the transport of a radionuclide was shown to be very significant when the apparent pseudo colloid formation constant, $K_{ap}(m^{3}/kg)$, was greater than 100. Thus, it can be concluded that acceleration of radionuclide migration may be occurred because the pseudo-colloid formation of radionuclides increases the amount of mobile components in the solution and consequently decreases the amount of radionuclides adsorbed on the stationary solid medium.

• 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.

• Nuclear Engineering and Technology
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• 제27권4호
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• pp.532-543
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• 1995

의사콜로이드에 의해 매개된 균열 암반 매질에서의 방사성 핵종의 이동 거동을 분석하고 예측하기 위한 이동모델이 개발되었다. 명목적인 의사콜로이드 형성 상수인 $K_{ap}$ (㎥/kg)값이 100보다 클 때 방사성 핵종의 이동에 매우 큰 영향을 미치는 것으로 나타났다. 계산결과에 의하면 Pu-239의 의사콜로이드형성 상수가 Ni-63보다 크기 때문에 Pu-239의 이동이 Ni-63보다 빠른 것으로 나타났다 따라서 결론적으로 균열 암반에서의 방사성 핵종의 가속화는 방사성 핵종과 자연성 참콜로이드와의 의사콜로이드 형성에 따른 용액에서의 유동성 성분의 증가와 방사성 핵종들의 정지된 고체매질로의 흡착양 감소에 기인함을 알 수 있다.

• 방사성폐기물학회지
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• 제6권2호
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• pp.129-139
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• 2008

본 연구에서는 국내산 경주벤토나이트를 이용하여 제조한 벤토나이트 콜로이드에 대한 산화환원 반응에 대체적으로 안정한 다가 핵종인 Eu(III)와 Th(IV)의 실험적 수착 연구를 수행하였다. 수착실험에 대한 공시험을 수행하여 반응용기 벽면에 의해, 침전에 의해, 콜로이드 형성에 의해 손실된 핵종들의 양을 평가하였다. 그리고 이러한 손실들을 반영한 Eu(III)와 Th(IV)의 벤토나이트 콜로이드에 대한 수착분배계수 $K_d$값을 구하고 조사하였다. 세 종류의 손실양을 반영한 벤토나이트 콜로이드의 순수한 수착분배계수 $K_d$ 값은 pH 변화에 따라 Eu(III)의 경우 $10^6-10^7mL/g$ 정도의 값을 가지고, Th(IV)의 경우 $7{\times}10^6-10^7\;mL/g$ 정도의 값을 가지는 것으로 관측되었다. 특히 Eu(III)의 경우엔 pH 5 이상에서 침전의 영향이 크게 나타났고, Th(IV)의 경우엔 pH 3 이후에 콜로이드 형성과 침전의 영향이 크게 나타났다. 따라서 주어진 농도에서 콜로이드 형성 및 침전 영향이 커지는 pH 이후에는 Eu(III) 및 Th(IV)과 같은 다가 핵종들의 정확한 수착분배계수를 구하기 위해서는 이러한 침전 및 콜로이드 형성과 같은 영향이 반영되어야 할 것이다.

• Bulletin of the Korean Chemical Society
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• 제29권12호
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• pp.2368-2372
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• 2008

• Nuclear Engineering and Technology
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• 제33권3호
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• pp.261-269
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• 2001

In this study, sorption experiments of uranium onto silica colloids were carried out and the effects of important geochemical parameters such as pH, ionic strength, carbonate concentration, colloid concentration, and total concentration of uranium were investigated. The sorption coefficients of uranium for silica colloids named as pseudo-colloid formation constants were about 10$^4$~ 10$^{5}$ mL/g depending on the experimental conditions. The effects of the geochemical parameters were found to be important in the sorption of uranium onto silica colloids. A Langmuir type sorption isotherm of uranium between silica colloids and the solution phase was also presented. The sorption mechanisms were explained by analyzing the effects of the geochemical parameters.

• Bulletin of the Korean Chemical Society
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• 제35권1호
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• pp.173-176
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• 2014

The hollow $SiO_2$ spheres with uniform size were synthesized by a modified Stober method under the control of polyelectrolytes (PSS and PAA) as templates. This synthetic route includes the formation of spherical colloid micelle in ethanol solution, hydrolysis of TEOS under control of ammonia, and the removal of polyelectrolyte by washing or calcination. Hollow silica spheres with controllable core diameters between 100 and 270 nm and wall thickness between 15 and 50 nm have been synthesized. The influence of template solution concentration and solvent and dispersant on the formation of silica hollow spheres is studied and reported in detail.

• 방사성폐기물학회지
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• 제4권3호
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• pp.235-243
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• 2006

본 연구에서는 현재 국내에서 고준위 방사성폐기물 처분장의 잠재적인 완충재 물질로 고려되고 있는 경주벤토나이트에서 발생 가능한 벤토나이트 콜로이드로의 우라늄(VI) 수착특성에 대한 실험적 연구를 pH 및 이온강도의 함수로 수행하였다. 경주벤토나이트로부터 분리된 콜로이드는 주로 몬모릴로나이트로 구성되어 있다. 중력여과법을 사용하여 측정한 결과 농도 및 크기는 약 5100 ppm 및 200-450 nm 이었다 우라늄 수착실험에 대한 공시험을 수행하여 수착 반응용기 벽면에 흡착, 침전, 한외여과에 의해 손실된 우라늄 양을 평가하였다. 이러한 과정에 의해 제거된 우라늄의 양은 미량이었다. 그러나 한외여과에 의한 우라늄 손실의 경우 이온강도가 낮은 경우 즉, 0.001 M $NaClO_4$의 경우 한외여과 필터의 표면전하 역전에 의한 양이온 수착 영향으로 인해 매우 높은 핵종 손실을 유발하였다. 벤토나이트 콜로이드에 대한 우라늄(VI)의 수착 분배계수 $K_d$ (또는 의사콜로이드 형성상수)는 PH 및 이온강도에 따라 $10^4{\sim}10^7 mL/g$ 값을 가지며 pH 중성영역인 6.5 근처에서 최대값을 가지는 것으로 나타났다. 벤토나이트에 대한 우라늄(VI)의 수착은 pH, 이온강도, 탄산농도 등과 같은 지화학적 변수들에 의존하는 수용액에서 우라늄화학종과 매우 밀접한 관련이 있다 따라서 벤토나이트 완충재로부터 발생된 벤토나이트 콜로이드는 높은 수착능으로 인해 우라늄(VI)을 의사콜로이드(pseudo-colloid)의 형태로 지질학적 매질을 통해 이동시킬 수 있을 것이다.

• 대한핵의학회지
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• 제3권1호
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• pp.73-82
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• 1969

The newly developed diagnostic method with application of $^{113}Sn-^{113m}In$ cow system ($^{113}Sn:\;T\frac{1}{2}$ 118 days, $^{113m}In:\;T\frac{1}{2}$ 1.7 hrs, 390 Kev, Single ${\gamma}$) has the remarkable advantages such as increased diagnostic ability by single large dose administration of $^{113m}In$ with no subsequent radiation hazard and shortened examining time. We reformed the research of following scope with the use of developed $^{113}Sn-^{113m}In$ cow (25 mCi) generator: The sizes of particles produced under various conditions were investigated, and possibility for application to the scannings of various organs such as brain, liver, lung, bone marrow and blood pool etc. were studied. Results: $^{113m}InCl_3$ solution eluted from diluted HCl solution (pH 1.5) passed through $^{113}Sn-^{113m}In$ generator, and there can be produced various sized particles of colloidal indium. And there observed the state of distribution of $^{113m}In$ in each organ which showed many differences according to the particle sizes of colloidal indium. The results are stated as follows: 1. The adjustment of pH is the most important factor in making the desirable particle size of colloidal indium. The colloid for blood pool showed the highest level as 7.1%/gm blood, at pH 1.7, the colloid of pH 3.5 for liver scanning showed the highest level, 88.4%, in the liver, the colloid pH 6 showed the highest level, 3.1%, in the spleen, and the colloid of pH 11.0 showed the highest level, 85.3%/gm, in the lung. 2. The colloid for liver scanning made with NaCl-NaOH system showed the highest liver uptake at pH 7.2, and at either higher or lower pH than 7.2 showed decrease of liver uptake more or less. 3. The activity of $^{113m}In$ eluted through $^{113}Sn-^{113m}In$ generator indicated over 90% in the initial 4 ml, and particularly 88.1%-86.0% in the initial 2 ml. 4. The incubation time, tempertaure and mechanical irritation related to colloid formation and coating of colloid were not the definite condition of influence.

• 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.