• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.60-70
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• 2003

The stability of various waste forms to meet waste acceptance criteria was evaluated by using standard test methods of U.S.A and France. Compressive strength of waste forms were above 176.03 kgf/$\textrm{cm}^2$(cement), 15 kgf/$\textrm{cm}^2$(paraffin). In the thermal cycling test, there were no any change in their feature and volume, the loss of weight was 6.15% on the average. In the immersion test for 120 days, the loss of weight of paraffin waste form was 8.85-5.14% pH=3.83. The G-Value of $H_2$ and $CH_4$ in paraffin wax at $10^8rads$ rads of exposure dose were 2.65, 0.016.

• 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.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.1 no.1
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• pp.93-103
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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 $^{60}$ Co and $^{137}$ Cs by ANS 16.1 method for waste forms of paraffin and cement were above 6.0. Their leaching behavior were depending on the type of matrix and leachant. Leachability of $^{60}$ Co for cement waste form was higher in simulated seawater than do-mineralized water, and was higher in de-mineralized water for paraffin waste form. leachability of $^{60}$ Co was contrary to $^{137}$ Cs. Cumulative fraction leached of $^{60}$ Co was higher in order or IAEA ＞ ANS ＞ FT in a cement waste form.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.278-283
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• 2005

Cement and paraffin waste form were prepared with a acid extraction method for the analysis of radionuclides generated from nuclear power plants. The acid extraction method was carried out with $HNO_3-HCl$ acid. At first, we compared the method with the microwave acid digestion method using SRM. The solutions of decomposed SRM were then analyzed by AAS and ICP-AES. The acid extraction method had shown good results as microwave acid digestion method. This method provided recovery values greater than $80\%$ for metallic elements.

• Applied Chemistry for Engineering
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• v.17 no.4
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• pp.391-396
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• 2006

When radioactive wastewater was solidified treatment by cement, the drying rate of cement and the volume reduction ratio was decreased because of boric acid component in the wastewater. In order to supplement the demerit, effects of paraffin wax investigated in this study. Paraffin wax has a hydrophobic properties and a low affinity with inorganic materials. When the radioactive wastewater was tested by a small of wax, the compressive strength of solidified waste are decreased Therefore boric acid in radioactive wastewater are first treated by alkali salt and coated by the stearic acid. During the solidification step, The amount of paraffin wax addition get the result that the compressive strength of solidification with cement was the same as that with paraffin wax. The leaching properties of radioactive waste solidified was the same CFL (cumulative fraction leached), PR (penetration rate), effective diffusivity if paraffin wax content in solidified waste was 20% or 25%.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.270.1-270
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• 2001

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.109-110
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• 2009

"드럼 코아시편 채취장치" 는 침출/내수성 시험, 압축강도 측정시험, 열 순환 시험등 의 파괴적 물성시험을 수행하기 위해서 경질(시멘트 고화체) 및 연질(파라핀왁스) 등의 방사성폐기물드럼으로부터 코아 시료를 채취하는 장비이다, 시편채취의 최대길이는 860 mm 이며 코아 시편의 직경은 50~200 mm 이며 일반적으로 "방사성폐기물 고화체의 물성시험"에 사용되는 시편은 실험실적으로 제조한 소규모 모의 고화체 시편과 고화공정에서 직접 채취한 소규모 시편, 200L 드럼으로부터 코아시편을 채취 가공하여 만든 시편과 같이 3종류가 있다. 고화공정에서 발생되는 고화체는 일반적으로 200 L 드럼에 주입되며, 고화체의 균일성 정도는 고화공정의 특성, 폐기물/고화매질 혼합비, 200 L 고화체 드럼의 냉각방식에 따라 다르다. 따라서, 실험실에서 제조한 시편과 공정에서 채취한 소규모시편은 실제 고화공정을 대표할 없으며 또한 실제 발생된 고화체의 조성과도 동일하다고 볼 수 없다. 따라서 200 L 드럼으로부터 코아시편을 채취하여 만든 시편이 고화공정과 고화체를 대표할 수 있는 시편으로 볼 수 있다 그러므로 고화체 및 고화공정을 대표할 수 있는 코아시편을 채취할 수 있는 장치를 제작하여 다양한 코아시편을 200 L 고화체 드럼으로부터 수직 코아시편을 채취할 필요가 있으며 실험에서 코아시편 채취속도와 연관된 Z-AXIS 의 Rpm은 운전범위는 0-2000 Rpm 이나 이때 너무 빠른 속도는 기계에 치명적인 손상을 초래 할 수 있으므로 위험한 것으로 나타났으며 500-1000 Rpm 의 속도가 적합한 것으로 시험되었으며 시편을 절삭하는 Spindle의 Rpm은 운전범위는 0-1500Rpm 이나 무리한 운전을 피해 가장 적절한 Speed로 운전해야하며 시험결과 500-800Rpm 이 최적운전범위로 나타났다 또한 시멘트고화체에서의 코아 채취시험에서는 Spindle의 속도는 500 Rpm, Z -AXIS 의 Rpm은 900 Rpm이 가장 적합한 것으로 나타났으며 성능평가시험을 통하여 비트부의 절삭속도와 Z축의 이동속도에 관한 그라프를 획득하였으며 시편의 크기에 따라서 Spindle의 속도를 증감하여야함을 확인할 수 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.361.1-361
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.335-335
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.309.2-309
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• 1999