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자료유형
학술저널
저자정보
박환서 (한국원자력연구원) 김인태 (한국원자력연구원) 김환영 (한국원자력연구원) 김준형 (한국원자력연구원)
저널정보
한국폐기물자원순환학회 한국폐기물자원순환학회지 한국폐기물자원순환학회지 제25권 제1호
발행연도
2008.1
수록면
43 - 49 (7page)

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Molten salt wastes from pyroprocess to recover uranium and transuranic elements are difficult to directly apply to vitrification or ceramization for the final disposal. In previous study, GRSS (Gel-Route Stabilization/Solidification) method as an alternative on the immobilization of salt wastes was suggested. This paper as a subsequent study investigated the leach-resistance on the solidified products prepared by using borosilicate glass with different compositions. By using a Si-P-Al gel-forming material system, the salt waste was treated to produce stable products after the gelation/aging/drying step. The gel product was mixed with glass powder and heat-treated at 1100℃ for 2 hrs. From the EPMA analysis, Si-rich phase in a gel product was dissolved into a given glass matrix while P-rich phase was encapsulated by the vitrified phase. At a optimum waste loading found by TG/DTA analysis and elemental analysis, there would be little vaporization during the heat-treatment at 1100. The leach rate of Cs and Sr were 10-²~10-³g/m²·day and 10-³ ~ 10-⁴g/m² · day, respectively, and was not greatly affected by the glass composition. The waste loading in GRSS method was two times over that in ANL method and its leach-resistance was comparable or superior to ANL method. From these results, it could be concluded that GRSS method is considered as an alternative on the immobilization method of molten salt waste for the final disposal.

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