• Nuclear Engineering and Technology
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• 제55권3호
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• pp.876-883
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• 2023

Radioactive waste should be solidified before being disposed of in the repository to eliminate liquidity or dispersibility. Cement is a widely used solidifying media for radioactive waste, and cement solidified waste should satisfy the minimum compressive strength of the waste acceptance criteria of a radioactive repository. Although the compressive strength of waste should be measured by the test method provided by the waste acceptance criteria, the method differs depending on the operating repository of different countries. Considering the measured compressive strength changes depending on test conditions, the effect of test conditions should be analyzed to avoid overestimation or underestimation of the compressive strength during disposal. We selected test conditions such as the height-to-diameter ratio, loading rate, and porosity as the main factors affecting the compressive strength of cement solidified radioactive waste. Owing to the large variance in measured compressive strength, the effects of the test conditions were analyzed via statistical analyses using parametric and nonparametric methods. The results showed that the test condition of the lower loading rate, with a height-to-diameter ratio of two, reflected the actual cement content well, while the porosity showed no correlation. The compressive strength assessment method that reflects the large variance of strengths was suggested.

• 방사성폐기물학회지
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• 제20권1호
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• pp.13-22
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• 2022

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

• 대한기계학회논문집A
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• 제21권9호
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• pp.1452-1461
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• 1997

The hot press apparatus to obtain the solidified rocks with 60mm of diameter against rock waste was developed, and the optimum conditions for solidification were founded out, of which were 300.deg. C of temperature and 1hr of holding time. The solidified rocks reinforced with the fibers (carbon, steel) were made by means of a hydrothermal hot press method. Fracture toughness of those was obtained using the round compact tension(RCT) specimens. Load and displacement behaviours of the solidified rocks reinforced with the fibers were dependent upon the fiber volume fraction and kind of the fibers. Strength and fracture energy of the solidified rocks with steel were much larger than those of the solidified ones with carbon because of the Bridge's effect, multiple cracking and crack branching phenomena.

• 한국산업융합학회 논문집
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• 제1권1호
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• pp.51-58
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• 1998

This study was carried out to investigate the leaching characteristics by the landfill of solidified sludge. pH of leachate was 3.7 - 5.8 and 8.0 - 10.4 in each column using sand as a top-soil layer on filled municipal waste and solidified cake. $NH_3$-N in leachate was increasing in the each column using sand as a top-soil layer on filled dewatered sludge and solidified cake, but decreasing in the each column using sand and solidified cake by top-soil layer on filled municipal waste. Also the concentration of $NO_3$-N was on the way of stabilizing but was difficult to find any tendency until now. Zn and Mn in leachates were the highest in the column filled with the solidified sludge, Cr, Pb and Cd were low concentration at each column.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.244-250
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• 2003

본 논문에서는 황사빗물이 중ㆍ저준위 방사성 폐기물 시멘트 고화체에 미치는 영향을 알아보았다. 실험은 ANS 16.1 실험법을 채택하였다. Co 핵종을 포함한 시멘트 고화체를 제작한 후, 대기 중 황사성분의 질량농도를 이용해 침출수의 부피, 이온 및 금속의 농도 등을 결정한다. 실험을 위해 대기 중 황사 부하량이나 강수에 포함되는 황사성분의 양, 처분장의 면적 등은 적합한 가정을 통해 결정하였다. 본 논문에서는 황사의 특성에 대해 간략히 소개하고 침출 실험의 준비과정으로 실험 조건을 결정한 후에, 90일간의 침출실험을 통해 나온 결과로 황사빗물에 의한 시멘트 고화체의 영향을 평가ㆍ분석하였다.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1524-1533
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• 2021

The structural stability of a waste package is essential for containing radioactive waste for the long term in a repository. A silo-type disposal facility would require more severe verification for the structural integrity, because of radioactive waste packages staked with several tens of meters and overburdens of crushed rocks and shotcretes. In this study, structural safety was analyzed for a silo-type repository, located approximately 100 m below sea level in Gyeongju, Korea. Finite element simulation was performed to investigate the influence of the loads from the backfilling materials and waste package stacks on the mechanical stress of the disposed of wastes and containers. It was identified that the current design of the waste package and the compressive strength criterion for the solidified waste would not be enough to maintain structural stability. Therefore, an enhanced criterion for the compressive strength of the solidified waste and several reinforced structural designs for the disposal concrete container were proposed to prevent failure of the waste package based on the results of parametric studies.

• 방사성폐기물학회지
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• 제16권1호
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• pp.83-91
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• 2018

우라늄 토양 및 콘크리트 폐기물의 동전기 제염 후 방사성폐기물의 시멘트 고화특성을 분석하기 위하여, 시멘트 고화 유동성 시험을 수행하고 시멘트 고화 시료를 제작하였다. 시멘트 고화시료에 대하여 압축강도, pH, 전기전도도, 방사선조사 효과 및 부피증가를 분석하였다. 방사성폐기물의 시멘트 고화의 작업 적정도는 175~190% 정도였다. 시멘트 고화시료의 방사선 조사 후 압축강도는 방사선 조사 전 압축강도 보다 약 15% 감소하였으나, 한국원자력환경공단 인수기준 ($34kgf{\cdot}cm^{-2}$)을 만족하였다. 동전기 제염 후 방사성폐기물의 시멘트 고화 시료에 대한 SEM-EDS 분석결과, 알루미늄상은 시멘트와 잘 결합한 형상을 나타낸 반면, 칼슘상은 시멘트와 분리된 형상을 나타내었다. 방사성폐기물의 시멘트 고화 부피는 시멘트에 대한 폐기물의 배합과 수분량에 따라 다르게 나타났다. 방사성폐기물의 시멘트 고화 부피(C-2.0-60)는 약 30% 증가였으며 동전기 제염 후 생성된 방사성폐기물의 영구처분은 적절하다고 판단되었다.

• 환경위생공학
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• 제18권4호
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• pp.36-44
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• 2003

The cement-based system among S/S(Solidification/Stabilization) is widely used to treat hazardous wastes. In this study, tannery sludge was solidified to evaluate the stabilization effects of using admixtures in the cement-based S/S. Fly ash as substitute also used to increase the strength of the S/S of hazardous waste. The compressive strength measurement and leaching experiment of chromium metal of solidified mortar were carried out to compare and evaluate the physical and chemical characteristics of solidified hazardous waste sludge. From the result of this study, there was increased of compressive strength by using AEW-3(early-hardening AE water reducing agent), and leaching concentration of chromium became low enough to satisfy the regulatory criteria. The successful solidification for the organic contaminant and heavy metal in hazardous waste should enable to treat by cement-based system using early-hardening AE water reducing admixture and fly ash as substituted cement.

• 한국지반환경공학회 논문집
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• 제2권1호
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• pp.15-22
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• 2001

고형화 폐기물의 처분에 대한 환경 위해성 평가의 핵심은 화학적 용출특성을 파악 후, 현장의 환경조건하에서 유해물질이 얼마나 주변환경으로 유출되는가를 예측하여 그 위해도를 산정하고, 그 위해도가 환경적으로 허용가능한 지를 판단하는 데 있다. 본 논문에서는 고형화폐기물을 매립지에 처분하거나 재활용시 다양한 현장조건하에서의 환경위해성을 평가하는 체계를 용출의 두 가지 극한적 경우에 입각하여 수립하였다. 수립된 위해성평가체계의 각 경우에 따른 폐기물 특성변수를 결정할 수 있는 두 종류의 특성평가기법을 개발하고, 시멘트 고화 처리된 도시쓰레기 소각재의 매립처분 현장에 적용하여 검증하였다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.194-195
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• 2018