Development of a carbonate crust on alkaline nuclear waste sludge at the Hanford site

2018 ◽  
Vol 342 ◽  
pp. 375-382 ◽  
Author(s):  
Jason S. Page ◽  
Jacob G. Reynolds ◽  
Tom M. Ely ◽  
Gary A. Cooke
Keyword(s):  
Nuclear Waste ◽  
Hanford Site ◽  
Waste Sludge ◽  
Carbonate Crust

History of the First Double-Shell High-Level Nuclear Waste Tank at the Hanford Site

CORROSION ◽  
10.5006/2922 ◽  
2018 ◽  
Vol 75 (3) ◽  
pp. 292-301
Author(s):  
J.A. Beavers ◽  
S. Chawla ◽  
K. Evans ◽  
B.C. Rollins ◽  
K.M. Sherer ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Hanford Site ◽  
History Of ◽  
High Level Nuclear Waste ◽  
High Level

scholarly journals Evaluation of Radionuclide Transport: Effect of Radionuclide Sorption and Solubility

1981 ◽  
Vol 11 ◽  
Author(s):  
P. F. Salter ◽  
G. K. Jacobs
Keyword(s):  
Nuclear Waste ◽  
The United States ◽  
Department Of Energy ◽  
Nuclear Waste Repository ◽  
Radionuclide Transport ◽  
Nuclear Wastes ◽  
Hanford Site ◽  
Transport Effect ◽  
Waste Repository ◽  
Engineered Barriers

The current strategy for the permanent isolation of nuclear wastes in the United States involves the storage of these wastes within repositories mined in deep geologic formations. In this disposal strategy, the isolation of nuclear wastes relies on a series of natural and engineered barriers to prevent the unacceptable release of radionuclides to the accessible environment. An integral part of the development of a qualified subsurface nuclear waste repository, therefore, is the assessment of the ability of these barriers to adequately prevent or retard the migration of radionuclides to the accessible environment. The Basalt Waste Isolation Project (BWIP) under guidance from the Department of Energy (DOE) is investigating the feasibility of storing nuclear w-stes in the basalts beneath the Hanford Site.

scholarly journals Nuclear waste: Sludge sites to be sought

Nature ◽  
1983 ◽  
Vol 305 (5936) ◽  
pp. 661-661
Author(s):  
Tim Beardsley
Keyword(s):  
Nuclear Waste ◽  
Waste Sludge

Large cemented gibbsite agglomerates in alkaline nuclear waste at the Hanford site and the impacts to remediation

2020 ◽  
Vol 384 ◽  
pp. 121318 ◽  
Author(s):  
Jason S. Page ◽  
Jacob G. Reynolds ◽  
Gary A. Cooke ◽  
Beric E. Wells
Keyword(s):  
Nuclear Waste ◽  
Hanford Site

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.

Evaluation of novel leaching assessment of nuclear waste glasses

MRS Advances ◽  
2016 ◽  
Vol 2 (11) ◽  
pp. 635-640
Author(s):  
Clare L. Thorpe ◽  
Russell J. Hand ◽  
Neil C. Hyatt ◽  
Albert A. Kruger ◽  
David S. Kosson ◽  
...  
Keyword(s):  
Coordination Chemistry ◽  
Nuclear Waste ◽  
Dissolution Behavior ◽  
Hanford Site ◽  
The Usa ◽  
Low Activity ◽  
Glass Compositions

ABSTRACTThis study investigates the use of ‘simple’ glasses, comprising six components, to represent the structure of complex LAW glasses proposed for Immobilized Low Activity Wastes from the Hanford site in the USA. The 18 elements present in ILAW glasses LAW A44, ORP LB2, and LAW A23 were represented by Al2O3, B2O3, CaO, Na2O, SiO2, and ZrO2 according to their coordination chemistry and their roles as network formers and modifiers. The dissolution behavior of each ‘simple’ glass was compared to its corresponding candidate “complex” LAW glass through PCT-B tests. Significant differences were observed; the durability of complex glasses was concluded to be LAW A44 > ORP LB2 ≥ LAW A23 whereas in their simplified versions the order was LAW A44 > LAW A23 > ORP LB2. These results are discussed in relation to compositional differences and highlight the importance of minor glass components in controlling glass durability. The implications of these results for the use of simplified glass compositions are discussed.

Gamma-Ray-Induced Destruction of Nitrilotriacetic Acid in a Simulated, Mixed Nuclear Waste: Radiolytic and Chemical Forces

1998 ◽  
Vol 3 (1) ◽  
Author(s):  
Anthony P. Toste
Keyword(s):  
Nuclear Waste ◽  
Gamma Ray ◽  
Nitrilotriacetic Acid ◽  
Hanford Site ◽  
Γ Radiation ◽  
Mixed Waste ◽  
Inorganic Waste

AbstractThis study explores the efficacy of γ-radiation for destroying nitrilotriacetic acid (NTA) in a simulated mixed waste, formulated to mimic a complex concentrate waste stored at the U. S. Department of Energy's Hanford Site. NTA was added to an inorganic waste matrix, which contained no radionuclides. The simulant then received a γ-dose of 7.5 × 1O

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