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High-level nuclear waste immobilization

Weber, W. J., Ewing, R. C. et al. 1998. Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium. Journal of Materials Research, 13, 1434-1484. [Pg.63]

T. Okura, N. Yoshida, Immobilization of Simulated High Level Nuclear Wastes with Li20-Ce02-Fe203-P20s Glasses, World Academy of Sci., Eng. Technol. 68 (2012) 265-270. [Pg.210]

Hench, L. L., Clark, D. E. Campbell, J. 1984. High level waste immobilization forms. Nuclear and Chemical Waste Management, 5, 149-173. [Pg.58]

The recovery of U and Pu in the closed nuclear fuel cycle usually produces an high level waste (HLW) stream containing high concentration of fission/activation products (e.g., U, Pu, Am, Eu, Sr) and process/structural materials (Fe, Ni, Cr, etc.). This concentrated HLW is typically submitted to immobilization in glass/ceramic matrices, followed by their disposal in geological repositories. Considering the half-lives of the fission products (in the range of hundred-millions years) this solution result is unsustainable. The treatment of HLW by SLM represents a possible alternative. [Pg.228]

See other pages where High-level nuclear waste immobilization is mentioned: [Pg.164]    [Pg.123]    [Pg.320]    [Pg.698]    [Pg.306]    [Pg.356]    [Pg.576]    [Pg.207]    [Pg.895]    [Pg.200]    [Pg.895]    [Pg.93]    [Pg.7040]    [Pg.3]    [Pg.14]    [Pg.37]    [Pg.38]    [Pg.89]    [Pg.75]    [Pg.194]    [Pg.332]    [Pg.94]    [Pg.114]    [Pg.690]    [Pg.695]    [Pg.85]    [Pg.26]    [Pg.37]    [Pg.303]    [Pg.63]    [Pg.886]    [Pg.886]    [Pg.350]    [Pg.7031]    [Pg.91]   
See also in sourсe #XX -- [ Pg.89 , Pg.90 ]



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