• Title/Summary/Keyword: 고화체

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Studies on the Physico-chemical Properties of Vitrified Forms of the Low- and Intermediate-level Radioactive Waste (중${\cdot}$저준위 방사성폐기물 유리고화체의 물리${\cdot}$화학적 특성 연구)

  • Kim, Cheon-Woo;Park, Byoung-Chul;Kim, Hyang-Mi;Kim, Tae-Wook;Choi, Kwan-Sik;Park, Jong-Kil;Shin, Sang-Woon;Song, Myung-Jae
    • Journal of the Korean Ceramic Society
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    • v.38 no.9
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    • pp.839-845
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    • 2001

  • In order to vitrify the Ion-Exchange Resin(IER), Dry Active Waste(DAW), and borate concentrate generated from the commercial nuclear facilities, the glass formulation study based on the their compositions was performed. Two glasses named as RG-1 and DG-1 were formulated as the candidate glasses for the vitrification of hte IER and DAW, respectively. A glass named as MG-1 was also formulated as a candidate glass for the vitrification of the mixed wastes containing the IER, DAW, and borate concentrate. The process parameters, product qualities, and economics were evaluated for the candidate glasses and confirmed experimentally for the some properties. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. the product qualities such as glass density, chemical durability, phase stability, etc. were satisfactory. In case of vitrifying the wastes using our developed glass formulation study, the volume reduction factors for the IER, DAW and mixed wastes were evaluated as 21, 89 and 75, respectively.

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Fly ash를 이용한 사용후핵연료의 유리화 가능성 및 내침출성 분석

  • 전관식;신진명;김종호
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.781-786
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    • 1995

  • 석탄화력발전소 산업부산물인 Fly ash를 이용한 고준위방사성폐기물의 붕규산 유리고화 가능성을 분석하였다. Fly ash SiO$_2$, NaNO$_3$, B$_2$O$_3$에 DUPIC 핵연료 제조공정으로부터 발생되는 모의 scrap waste를 20 wt% 혼합하여, l15$0^{\circ}C$ 에서 3시간 용융시켜 붕규산유리화시켰다. 또한 붕규산유리고화체의 침출성을 평가하기 위하여 2일동안의 soxhlet 침출실험결과 양호한 내침출성을 보였다. 또한 고체폐기물의 안정화물질로 fly ash를 사용할 경우 fly ash 함량을 57%까지 첨가하여도 붕규산유리고화체의 제조가 가능함을 확인하였으며, fly ash의 첨가로 인한 유리화원료 재료비를 30% 까지는 절감시킬 수 있을 것으로 예상된다.

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Determination of Forward Dissolution Rate of Glass by a Single-Pass Flow-Through Test (Single-Pass Flow-Through Test방법에 의한 유리의 정용해율 측정)

  • Kim Seung-Soo;Chun Kwan-Sik;Choi Jong-Won;Kim Sung-Ki;Hahn Pil-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.4
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    • pp.335-340
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    • 2005

  • The forward dissolution rate of a borosilicate waste glass was determined as an interlaboratory study(ILS) testing program for the evaluation of precision in the measurement of the dissolution rate or a waste glass using a single-pass flow-through(SPFT) test, whose conducting practice has been written for standardization through American Society for Testing and Materials (ASTM). A simulated low-activity waste glass powder with a size of 100/200 mesh was dissolved by lithium buffer solution (pH=10) at 70? under Ar atmosphere. By plotting the dissolution rates as a function of silicon and boron concentration in eluate, the forward dissolution rate of the glass was obtained as about $2.7\times10^{-5}g{\cdot}m{\cdot}s^{-1}$ in our laboratory.

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