• 방사성폐기물학회지
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• 제18권4호
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• pp.517-536
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• 2020

The radionuclide inventory in radioactive waste from nuclear power plants should be determined to secure the safety of final repositories. As an alternative to time-consuming, labor-intensive, and destructive radiochemical analysis, the indirect scaling factor (SF) method has been used to determine the concentrations of difficult-to-measure radionuclides. Despite its long history, the original SF methodology remains almost unchanged and now needs to be improved for advanced SF implementation. Intense public attention and interest have been strongly directed to the reliability of the procedures and data regarding repository safety since the first operation of the low- and intermediate-level radioactive waste disposal facility in Gyeongju, Korea. In this review, statistical methodologies for SF implementation are described and evaluated to achieve reasonable and advanced decision-making. The first part of this review begins with an overview of the current status of the scaling factor method and global experiences, including some specific statistical issues associated with SF implementation. In addition, this review aims to extend the applicability of SF to the characterization of large quantities of waste from the decommissioning of nuclear facilities.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.610-611
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.335-336
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• 2019

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.207-208
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• 2017

• 방사선산업학회지
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• 제17권4호
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• pp.501-508
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• 2023

There are various factors that have a negative impact on safety over a long period of time after the closure of a radioactive waste disposal facility. In particular, it is important to limit substances that accelerate radionuclide migration while inhibiting adsorption between radionuclides and the subsurface medium. Through this study, a method for deriving a quantitative criteria evaluation method is proposed for cellulose among materials that accelerate the movement of these radionuclides after closure of the disposal facility. Since Sweden's SKB is representative worldwide for preparing criteria for cellulose in disposal facilities, it analyzed Sweden's acceptance criteria method and presented a method that can be applied domestically. The decomposition characteristics of cellulose and the adsorption and dissolution characteristics of ISA among degradation products were reviewed, and quantitative analysis of cement materials that create a high pH environment favorable for cellulose decomposition was also included. In addition, the total amount of the finally disposable cellulose material can be derived by using the volume information of the waste containing the cellulose material. Through this methodology for calculating the total amount of cellulose, it is expected that subsequent studies will be conducted to secure data reflecting the environmental conditions of radioactive waste disposal facilities in Korea. In addition, it is expected to be utilized as a good method to evaluate the impact of other complexing agents other than cellulose and to suggest the amount of disposal.

• 한국세라믹학회지
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• 제48권5호
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• pp.454-457
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• 2011

We report the preparation of nanocrystalline cobalt ferrite, $CoFe_2O_4$, particles using recycled $Co_3O_4$ and their surface coating with silica using micro emulsion method. Firstly, the $Co_3O_4$ powders were separated from waste cemented carbide with acid-base chemical treatment. The cobalt ferrite nanoparticles with the size 10 nm are prepared by thermal decomposition method using recycled $Co_3O_4$. $SiO_2$ was coated onto the $CoFe_2O_4$ particles by the micro-emulsion method. The $SiO_2$-coated $CoFe_2O_4$ particles were studied their physical properties and characterized by X-ray diffraction (XRD), high resolution-transmission electron microscopy (TEM) analysis and CIE Lab value.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2006년도 춘계 학술발표회 논문집(II)
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• pp.109-112
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• 2006

Social and environmental pressures draw greater significance on the recycling of the waste. Particularly, waste concrete is particularly crucial among the construction wastes in terms of conservation of natural construction resources as well as disposal crisis. The technology to recycle the waste concrete has been improved. This study has various replacement levels of natural fine aggregate with recycled fine aggregate while coarse aggregate is completely replaced with the recycled coarse aggregate and herein fundamental properties investigated include compressive strength, shrinkage and dynamic modulus of elasticity. As a result, it is anticipated that the recycled aggregate concrete can be successfully applied to structural concrete members provided a proper recycling process, mix design and curing method are practiced.

• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.81-87
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• 2020

Background: Kori unit #1 is permanently shut down after a 40-year lifetime. The Nuclear Safety and Security Commission recommends establishing initial decommissioning plans for all nuclear and radwaste treatment facilities. Therefore, the Korea Atomic Energy Research Institute (KAERI) must establish an initial and final decommissioning plan for radwaste-treatment facilities. Radiation safety assessment, which constitutes one chapter of the decommissioning plan, is important for establishing a decommissioning schedule, a strategy, and cost. It is also a critical issue for the government and public to understand. Materials and Methods: This study provides a method for assessing external radiation dose to workers during decommissioning. An external dose is calculated following each exposure scenario, decommissioning strategy, and working schedule. In this study, exposure dose is evaluated using the deterministic method. Physical characterization of the facility is obtained by both direct measurement and analysis of the drawings, and radiological characterization is analyzed using the annual report of KAERI, which measures the ambient dose every month. Results and Discussion: External doses are calculated at each stage of a decommissioning strategy and found to increase with each successive stage. The maximum external dose was evaluated to be 397.06 man-mSv when working in liquid-waste storage. To satisfy the regulations, working period and manpower must be managed. In this study, average and cumulative exposure doses were calculated for three cases, and the average exposure dose was found to be about 17 mSv/yr in all the cases. Conclusion: For the three cases presented, the average exposure dose is well below the annual maximum effective dose restriction imposed by the international and domestic regulations. Working period and manpower greatly affect the cost and entire decommissioning plan; hence, the chosen option must take account of these factors with due consideration of worker safety.

• 자원리싸이클링
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• 제23권4호
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• pp.30-36
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• 2014

자동차 산업의 발달과 함께 환경오염 문제가 심각해지면서 연간 300,000톤 이상 발생하는 폐타이어의 재활용에 대한 관심이 높아지고 있다. 본 연구에서는 폐타이어 재활용을 목적으로 40, 80, 140 mesh 크기의 폐타이어 분말을 선별한 후, 입도 분석을 통하여 크기를 확인하고 그 형상을 SEM을 통해 관찰하였다. 또한 각각의 폐타이어 분말을 Virgin PP와 혼합하고 Intermeshing Corotating Twin Screw Extruder를 이용하여 TPV를 제조하고 특성 분석을 하였다. 이 중 효과가 좋은 140 mesh의 폐타이어 분말과 Virgin PP, Waste PP, PP-g-MA 세 가지 종류의 매트릭스를 다양한 비율로 혼합하여 TPV를 제조한 후 UTM을 통한 인장강도, 연신율과 Izod impact로 충격강도 등을 측정하였고 TGA로 열안정성을 확인하였다. 또한 SEM을 통하여 폐타이어 분말의 분산정도 및 파단면을 확인하였다.

• 방사성폐기물학회지
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• 제18권2_spc호
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• pp.227-235
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• 2020

우리는 실험과 MCNP 시뮬레이션을 통해 전알파 분석법의 한계를 설명하였다. 국내에서 중·저준위 방사성폐기물 인도 규정 관련, 전알파 분석법은 방사성폐기물을 처분하기 위해 반드시 규명해야 할 방사성 특성평가 인자이다. 전알파 분석법은 시료 준비 절차가 간단하고 신속한 분석 결과를 제공하지만, 정량분석 인자로 사용하는 것은 적절하지 않다. KCl과 ²⁴¹Am을 이용하여 시편 건조고형물 무게에 따른 전알파 계측효율을 평가하였다. 동일한 무게의 시편일지라도 계측효율의 차이가 20% 나는 것을 확인하였고, 이는 시편의 물리적 형태가 서로 다르기 때문인 것으로 보인다. 토양 중 우라늄을 화학분리 한 후, ICP-MS로 우라늄을 직접 측정한 결과와 전알파 농도를 비교하였다. 전알파는 실제 우라늄 농도에 비해 50% 과소평가되었다. 알파핵종별 전알파 계측효율이 최대 3배 차이 나기 때문에, 전알파 분석결과는 개별 알파핵종의 합과 비교하기 보다는 스크리닝 개념으로 사용하는 것이 적절하다.