scholarly journals Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

2020 ◽  
Vol 4 (1) ◽  
Author(s):  
Xiaolei Guo ◽  
Stephane Gin ◽  
Gerald S. Frankel
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Solution Chemistry ◽  
Metal Alloys ◽  
Waste Forms ◽  
Open Questions ◽  
Environmental Attributes ◽  
Temperature Solution ◽  
High Level Nuclear Waste ◽  
High Level

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.

High level nuclear waste isolation: borosilicate glass versus crystals

Nature ◽  
1979 ◽  
Vol 278 (5701) ◽  
pp. 210-212 ◽  
Author(s):  
G. de Marsily
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
High Level Nuclear Waste ◽  
High Level

scholarly journals Apatite- and Monazite-Bearing Glass-Crystal Composites for the Immobilization of Low-Level Nuclear and Hazardous Wastes

1995 ◽  
Vol 412 ◽  
Author(s):  
D. J. Wronkiewicz ◽  
S. F. Wolf ◽  
T. S. DiSanto
Keyword(s):  
Transition Metals ◽  
Nuclear Waste ◽  
Toxic Metals ◽  
Hazardous Wastes ◽  
Waste Streams ◽  
Waste Forms ◽  
Glass Crystal ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Crystal Composite

AbstractThis study demonstrates that glass-crystal composite waste forms can be produced from waste streams containing high proportions of phosphorus, transition metals, and/or halides. The crystalline phases produced in crucible-scale melts include apatite, monazite, spinels, and a Zr-Si-Fe-Ti phase. These phases readily incorporated radionuclide and toxic metals into their crystal structures, while corrosion tests have demonstrated that glass-crystal composites can be up to 300-fold more durable than simulated high-level nuclear waste glasses, such as SRL 202U.

Chemical structure and dissolution behaviour of CaO and ZnO containing alkali-borosilicate glass

2022 ◽  
Author(s):  
Adam J Fisher ◽  
Hao Ding ◽  
Prashant Rajbhandari ◽  
Brant Walkley ◽  
Lewis R Blackburn ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Chemical Structure ◽  
Sodium Borosilicate Glass ◽  
Waste Vitrification ◽  
Dissolution Behaviour ◽  
High Level Nuclear Waste ◽  
High Level

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...

Advanced Ceramics and Glass-Ceramics for Immobilisation of ILW and HLW

2012 ◽  
Vol 1475 ◽  
Author(s):  
E. R. Vance ◽  
M. W. A. Stewart ◽  
S. Moricca
Keyword(s):  
Nuclear Waste ◽  
Hot Isostatic Pressing ◽  
Glass Ceramics ◽  
Steady Increase ◽  
Waste Forms ◽  
Regulatory Guidelines ◽  
Small Footprint ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Interim Storage

ABSTRACTSince the 1970s there has been a steady increase in research on candidate ceramic and glass-ceramics for immobilisation of HLW and ILW, both from the aspects of crystal-chemical design and processing technology. The variety of ceramics and glass-ceramics designed for different types of HLW and ILW will be presented, notably those which are problematic for vitrification. Several of these materials are optimally processed by hot isostatic pressing (HIP), a technology which can consolidate calcined intermediate-level and high-level nuclear waste. Thus we are targeting such wastes for development of alternative waste forms. The essential process steps during the HIP cycle will be outlined. Effective consolidation of a wide variety of tailored glass-ceramic and ceramic waste forms has been demonstrated. The principal advantages of the HIP technology include negligible offgas during the high temperature consolidation step, relatively small footprint, and high waste/volume loadings. While it can be argued that the “nuclear waste problem” is essentially solved technically, at least with current regulatory guidelines, different perceptions of the “best” waste form and processing method for a given waste, together with the general current lack of agreed locations for final repositories, or even interim storage sites, create uncertainties.

The reaction of reference commercial nuclear waste glasses during gamma irradiation in a saturated tuff environment

1988 ◽  
Vol 3 (3) ◽  
pp. 576-597 ◽  
Author(s):  
John K. Bates ◽  
William L. Ebert ◽  
Donald F. Fischer ◽  
Thomas J. Gerding
Keyword(s):  
Gamma Irradiation ◽  
Radiation Exposure ◽  
Nuclear Waste ◽  
Current Data ◽  
Solution Chemistry ◽  
Nuclear Waste Repository ◽  
Exposure Rate ◽  
Reaction Products ◽  
High Level Nuclear Waste ◽  
High Level

The effects of gamma irradiation on groundwater and the reaction between groundwater and glass have been investigated at radiation exposure rates of 2 × 105 1 × 103 and 0 R/h. These experiments, which bound the conditions that may occur in a high-level nuclear waste repository located in tuff, have been performed using the actinide-containing glasses ATM-lc and ATM-8, and have been performed for time periods up to 278 days. The experimental results indicate that when only the repository groundwater is present, the pH of the system remains near-neutral, regardless of the radiation field, due to the buffering capacity of the solution. When glass is added to the system, the subsequent reaction is governed by the solution chemistry, which results from a complex interaction between radiolysis products, glass reaction products, and groundwater components. While no long-term reaction trends have been extracted from the current data, it is noted that there are no outstanding differences in the reaction of the glasses as measured by the release of the soluble components B, Mo, and Na, as a function of radiation exposure rate. However, there is a marked difference in the amount of U, Np, and Pu released from the glasses as a function of radiation exposure rate. This difference can be correlated with the pH values of the leachate, with more basic solutions resulting in lower actinide release.

Synthesis of pyrochlore-borosilicate glass-ceramics for immobilization of high-level nuclear waste

2020 ◽  
Vol 46 (5) ◽  
pp. 6085-6094 ◽  
Author(s):  
Kangming Wu ◽  
Fu Wang ◽  
Qilong Liao ◽  
Hanzhen Zhu ◽  
Dongsheng Liu ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Glass Ceramics ◽  
High Level Nuclear Waste ◽  
High Level

Initial Demonstration of the Vitrification of High-Level Nuclear Waste Sludge Containing an Organic Cs-Loaded Ion-Exchange Resin

1992 ◽  
Vol 294 ◽  
Author(s):  
N. E. Bibler ◽  
J. P. Bibler ◽  
M. K. Andrews ◽  
C. M. Jantzen
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Exchange Resin ◽  
Ion Exchange Resin ◽  
Waste Sludge ◽  
New Process ◽  
The Usa ◽  
High Level Nuclear Waste ◽  
High Level

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.

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