• Nuclear industry
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• v.6 no.12 s.46
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• pp.120-122
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• 1986

미국원자력학회가 주최한 ${\ulcorner}$SPECTRUM '86-폐기물처리처분 및 제염과 폐로회의${\lrcorner}$가 '세계의 방사성폐기물관리 현황과 장래'를 기조테마로 지난 9월 14일부터 18일까지 17개국에서 600여명이 참가한 가운데 열려, 고$\cdot$저준위폐기물처리처분에 대한 경험과 계획, 제염과 폐로 등에 관해서 폭넓게 논의되었다. 다음은 이 회의에서 소개된 선진각국에서의 유리고화플랜트 현황과 처분계획을 요약한 것이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.3
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• pp.221-227
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• 2010

The solidification methods for powder wastes dried at CWDS(Concentrate Waste Drying System) in PWR have been studied in a variety of ways both at home and abroad. The solidification for these wastes has been performed using stabilization agents such as cement, paraffin and polymer. The applicability studies to maximize the reduction ratio of wastes and operational effectiveness for wastes treatment have been carried out, recently. It is necessary to pretreat the powder wastes before feeding wastes to vitrification facility because the fines flying brings about clogging of feeding pipes and off-gas treatment system or workers' exposure to radiation during maintenance. This paper describes an effective method for treatment of powder wastes to improve safety and stability of vitrification facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.319-320
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• 2015

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.4
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• pp.271-280
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• 2013

Since the decommissioning of nuclear plants and facilities, large quantities of slightly contaminated concrete waste have been generated. In Korea, the decontamination and decommissioning of the KRR-1, 2 at the KAERI have been under way. And concrete waste was generated about 800 drums of 200 L. The conditioning of concrete waste is needed for final disposal. The concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled void space after concrete rubble pre-placement into 200 L drum. Thus, this research has developed an optimizing mixing ratio of concrete waste, water, and cement and has evaluated characteristics of a cement waste form to meet the requirements specified in disposal site specific waste acceptance criteria. The results obtained from compressive strength test, leaching test, thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested to have 75:15:10wt% as the optimized mixing ratio. Also, the compressive strength of cement waste form was satisfied that including fine powder up to maximum 40wt% in concrete debris wastes about 75%. As a result of scale-up test, the mixture of concrete waste, water, and cement is 75:10:15wt% meet the satisfied compressive strength because the free water increased with and increased in particle size.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.186-190
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• 2003

유리고화체의 내구성과 조성에 관한 이 연구의 목적은 구조적 모델, 비가교 산소 모델(NBO) 및 간단한 경험적 모델(Valence-oxygen)과 함에 침출실험결과들을 비교하는 것이다. 조성에 기초한 모델들 사이의 연관성들은 이와 같은 모델들이 지질학적 유리와 제조된 유리의 관련성에 대해 유리고화체의 내구성을 설명할 수 있다는 것을 나타낸다 이러한 관계는 유리고화체의 장기간 내구성을 결정하는데 도움을 줄 수 있으며, 모델을 통한 유리고화체의 조성에 의한 실험결과에의 영향성을 검토하였다 9$0^{\circ}C$에서 7일간 수행된 PCT 침출시험을 대상으로 모델들을 비교하였으며 Ash Loading wt%가 증가할수록 망목형성이온이 증가하기 때문에 침출농도 및 침출분율이 감소하는 것을 확인 할 수 있었으며, VO model의 변수 값이 증가할수록 주요 유리매질의 침출분율은 완만한 기울기를 가지며 감소하다. 금속류의 침출분율은 VO model의 변수 값이 감소함에 따라 대체적으로 증가함을 확인 할 수 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.319-323
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• 1997

석탄화력발전소의 부산물인 석탄회를 이용한 DUPIC dirty scrap waste의 유리고화체에 대한 내침출성을 분석하였다. Fly ash, SiO$_2$, NaNO$_3$, B$_2$O$_3$에 DUPIC 핵연료 제조공정으로부터 발생되는 모의 dirty scrap waste를 15 wt% ~ 30 wt% 혼합하여, 115$0^{\circ}C$ 에서 3시간 용융시킨 후 서서히 냉각시켜 얻은 유리고화체의 침출성을 온도, 침출액의 종류, 폐기물의 함량 등에 따라 평가하였다 침출실험결과 석탄회유리고화체는 양호한 내침출성을 보였다. 석탄회유리고화체의 침출율은 합성지하수, 합성해수, 증류수의 순으로 감소하였으며, 폐기물함량의 증가에 따라 증가하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.244-250
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• 2003

With a recent public concern rising on the radioactive waste, it is disclosed that the problem is more serious than expected. This research has been conducted to find effects of yellow sandy rainwaters on the solidified cement of mid-and-low level radioactive waste. The ANS 16.1 standard test method was chosen for this leaching experiment. Make a cement solidified radioactive waste that contains Co nuclide, and fabricate it for over 28 days. Then, decide on the volume of leaching water and the concentration of ion and metal in leachate from the mass concentration of yellow sands in atmosphere. In this paper, we have taken a short look at characteristics of yellow sand. Before going into the leaching experiment, we decided experimental conditions first. Then, it was evaluated and analyzed how sandy rainfalls have impact on the cement solidified radioactive waste based on data from 90 days of leaching experiment.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.1 no.1
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• pp.41-46
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• 2003

To understand the long-term leach behavior of a borosilicate Waste glass in a repository, the leaching experiment with three kinds of simulated borosilicate waste glasses has been carried out since the middle of 1997. The five years results indicate that a boron would be applied as an indicator of a long-term leaching of their borosilicate waste glasses and that their long-term leach rates have a tendency to be close to about 0.03g/$m^2$-day even though their compositions and their ratios of the surface area to the volume of leachate are different.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.193-194
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.21-31
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• 2003

IAEA, FT-04-020, and ANS 16.1, standard leaching test methods, were evaluated comparatively with their test results. Leaching index of Co-60 and Cs-137 for all waste forms were above 6.0. Their leaching behavior were contrary according to the type of matrix and leachant. Leachability of Co in cement waste form was higher in simulated seawater than demi. water, and higher in demi. water in paraffin waste form. Leachability of Cs was contrary to Cs. Cumulative fraction leached of Co was higher such as IAEA＞ANS＞FT in cement waste form.