• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.299-300
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2012.10a
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• pp.191-192
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2012.10a
• /
• pp.403-404
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.441-442
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• 2015

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2012.05a
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• pp.313-314
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2012.05a
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• pp.89-90
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• 2012

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.207-212
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• 1996

실증규모의 수지충전식 전기투석 재생조를 사용하여 농축음극액내 바나듐의 전기화학적 환원 방법에 의한 재생거동을 조사하였다. 전기투석 분리재생 종료후 남아있는 개미산용액을 전해액으로 사용한 농축음극액내 전기투석된 철 및 코발트는 음극액의 pH를 약 4.3내외로 조절하면 전해환원에 의해 전착.제거된다. 또한 농축음극액내 바나듐은 +2가로 전해환원 되어 착화물을 이루고 있는 Vanadous picolinate 형태로 존재하기 때문에 음극액은 농축된 LOMI 제염제로 재생된다. 이 전해환원에 의한 농축음극액의 재생방법은 제염폐액의 전기투석 분리재생 후 피콜리네이트 착화제만을 재사용하는 기존의 재생개념보다 더욱 효과적으로 제염폐액을 재생시켜 재활용할 순 있는 방사성폐기물의 감용효율이 큰 향상된 제염폐액 재생공정이다.

• Journal of Biosystems Engineering
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• v.26 no.1
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• pp.67-73
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• 2001

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.2
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• pp.91-101
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• 2007

In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver.3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and $0.05515Bq/cm^2$ (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is $0.01Bq/cm^2\;for\;{\alpha}-emitter$ and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of $^{238}U$, below 2w/o for enrichment of $^{235}U$ and 0.0089Bq/g for artificial contamination of $^{238}U$ respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No.2001-30 of the MOST and Korea Atomic Energy Act.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.284-289
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• 2005

According to the nuclear safety regulation policy including the administration of radionuclides in low level radwastes, the evaporator bottoms were mixed with cement to form a stable solidification for identifying the recovery possibility of the C-14. The chemical oxidation method was applied for the extraction of C-14 from the cement waste form. The emitting beta ray of the C-14 extracted from the radwastes was measured with the liquid scintillation counter and calculated by using the quenching correction curves. Only the beta emitting radioactive nuclides of the C-14 in the radwastes was showed the radioactivities with the range of $2.7E+00\;{\sim}\;3.07E+02$ Bq/g.