scholarly journals Molten Salt and Surface Finishing. Pyrochemical Reprocessing for Spent Nuclear Fuel and Dry Separation Process for Radioactive Waste. Separation of Fission Products with Electrorefining in Molten Salt.

1998 ◽  
Vol 49 (4) ◽  
pp. 356-360 ◽  
Author(s):  
Reiko FUJITA
Keyword(s):  
Radioactive Waste ◽  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Separation Process ◽  
Surface Finishing ◽  
Waste Separation ◽  
Pyrochemical Reprocessing

scholarly journals Natural Clay Minerals as a Starting Material for Matrices for the Immobilization of Radioactive Waste from Pyrochemical Processing of SNF

2021 ◽  
Vol 13 (19) ◽  
pp. 10780
Author(s):  
Anna V. Matveenko ◽  
Andrey P. Varlakov ◽  
Alexander A. Zherebtsov ◽  
Alexander V. Germanov ◽  
Ivan V. Mikheev ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Fuel ◽  
Storage Time ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Bentonite Clay ◽  
Ceramic Materials ◽  
High Level Waste ◽  
Natural Clay ◽  
High Level

Pyrochemistry is a promising technology that can provide benefits for the safe reprocessing of relatively fresh spent nuclear fuel with a short storage time (3–5 years). The radioactive waste emanating from this process is an electrolyte (LiCl–KCl) mixture with fission products included. Such wastes are rarely immobilized through common matrices such as cement and glass. In this study, samples of ceramic materials, based on natural bentonite clay, were studied as matrices for radioactive waste in the form of LiCl–KCl eutectic. The phase composition of the samples, and their mechanical, hydrolytic, and radiation resistance were characterized. The possibility of using bentonite clay as a material for immobilizing high-level waste arising from pyrochemical processing of spent nuclear fuel is further discussed in this paper.

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