High level nuclear waste isolation: borosilicate glass versus crystals

Nature ◽  
1979 ◽  
Vol 278 (5701) ◽  
pp. 210-212 ◽  
Author(s):  
G. de Marsily
2022 ◽  
Author(s):  
Adam J Fisher ◽  
Hao Ding ◽  
Prashant Rajbhandari ◽  
Brant Walkley ◽  
Lewis R Blackburn ◽  
...  

Within the context of the UK’s radioactive waste vitrification programme, which utilises a lithium-sodium borosilicate glass modified with CaO and ZnO to immobilise high level nuclear waste, an investigation was...


2020 ◽  
Vol 4 (1) ◽  
Author(s):  
Xiaolei Guo ◽  
Stephane Gin ◽  
Gerald S. Frankel

Abstract This review covers the corrosion interactions between different materials that are relevant to the disposal of high-level nuclear waste, in particular the waste forms and containers. The materials of interest are borosilicate glass, crystalline ceramics, metal alloys, and any corrosion products that might form. The available data show that these interactions depend on the structure, chemistry, thermodynamic history, and proximity of the materials in contact, as well as the environmental attributes, such as temperature, solution chemistry, and radiation. Several key mechanisms that govern these interactions are highlighted. Scientific gaps and open questions are summarized and discussed.


2020 ◽  
Vol 46 (5) ◽  
pp. 6085-6094 ◽  
Author(s):  
Kangming Wu ◽  
Fu Wang ◽  
Qilong Liao ◽  
Hanzhen Zhu ◽  
Dongsheng Liu ◽  
...  

1992 ◽  
Vol 294 ◽  
Author(s):  
N. E. Bibler ◽  
J. P. Bibler ◽  
M. K. Andrews ◽  
C. M. Jantzen

ABSTRACTWhen immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. A resorcinol based organic ion exchange resin is used. This resin was then mixed with sludge and frit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. For example, use of the zeolite increases the amount of glass to be made and use of the organic precipitant produces benzene as a secondary waste stream. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. However, when resin is present in the feed, the glass becomes less durable due to the increased amount of Fe(II) caused by reduction of Fe(III) in the melt. Based on the durabilities of other waste glasses, this glass is still suitable as a canistered wasteform.


2020 ◽  
Vol 86 (7-8) ◽  
pp. 247
Author(s):  
S. MANDAL ◽  
S. SEN ◽  
S. GHORUI ◽  
S. BARIK ◽  
P G PAL CHOWDHURY ◽  
...  

2013 ◽  
Vol 3 (1) ◽  
pp. 60-69 ◽  
Author(s):  
Hamid Aït Abderrahim ◽  
Didier De Bruyn ◽  
Gert Van den Eynde ◽  
Sidney Michiels

2021 ◽  
pp. 153423
Author(s):  
José Marcial ◽  
Jaroslav Kloužek ◽  
Miroslava Vernerová ◽  
Pavel Ferkl ◽  
SeungMin Lee ◽  
...  

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