Strontium-Basalt Reactions Under Nuclear Waste Repository Conditions

1981 ◽  
Vol 6 ◽  
Author(s):  
Sridhar Komarneni
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Confining Pressure ◽  
Main Mechanism ◽  
Nuclear Waste Repository ◽  
Strontium Chloride ◽  
Nuclear Wastes ◽  
Basalt Glass ◽  
Mineral Phases ◽  
Waste Repository

ABSTRACTHydrothermal interactions of Sr as strontium chloride or hydroxide with basalts or basalt phases were investigated at 300°C for 4 and/or 12 weeks under a confining pressure of 30MPa. The nature and extent of Sr immobilization varied with the Sr source and with the basalt or basalt phase which immobilized up to 99.99% of the added Sr. The main mechanism of Sr fixation with basalts seems to be ion exchange when SrCl2 was the Sr source. Among the basalt phases, basalt glass was the most effective for SrCl2 immobilization by probably forming new strontium mineral phases. However, when Sr(OH)2 reacted with basalts or basalt phases Sr was immobilized by the crystallization of strontium aluminosilicates such as SrAl2Si2O8 . These results of Sr-nearfield interactions in a basalt repository indicate that basalt can be a good barrier for Sr migration from nuclear wastes.

scholarly journals Radiation Effects on Materials in the Near-Field of a Nuclear Waste Repository

2000 ◽  
Vol 663 ◽  
Author(s):  
B.X. Gu ◽  
L.M. Wang ◽  
S.X. Wang ◽  
R.C. Ewing
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Radiation Effects ◽  
Ion Beam ◽  
Near Field ◽  
Energetic Electron ◽  
Layered Silicates ◽  
Nuclear Waste Repository ◽  
Layer Spacing ◽  
Waste Repository

ABSTRACTThe long-term radiation effects on materials in the near-field of a nuclear waste repository have been evaluated using accelerated laboratory experiments with energetic electron or ion beam irradiation. The materials studied include: zeolites, layered silicates (smectite clay and mica), as well as crystalline silicotitanate (CST) which is an important ion exchange material for the chemical separation of high-level liquid radioactive wastes.In situ transmission electron microscopy (TEM) during irradiation by energetic electrons and ions has shown that all of the studied materials are susceptible to irradiation-induced amorphization. At room temperature, complete amorphization was observed after ionizing doses of 1010 ∼ 1012 Gy or displacement doses on the order of 0.1 dpa (equivalent to doses received in 400-1,000 years for a high-loading nuclear waste form). Amorphization may be preceded or accompanied by dehydration, layer spacing reduction and gas bubble formation. In the case of zeolites, CST and some layered silicates, radiation effects are significantly enhanced at higher temperatures. Our experiments have shown that amorphization or even partial amorphization will cause a dramatic reduction in ion exchange and sorption/desorption capacities for radionuclides, such as Cs and Sr. Because the near-field or chemical processing materials (e.g. zeolites or CST) will receive a substantial radiation dose after they have incorporated radionuclides, our results suggest that radiation effects may, in some cases, retard the release of sorbed or ion-exchanged radionuclides.

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.

Chemical, Physical and Engineering Characterization Of Candidate Backfill Clays and Clay Admixtures for a Nuclear Waste Respository-Part I

1981 ◽  
Vol 6 ◽  
Author(s):  
Sudesh K. Singh
Keyword(s):  
Nuclear Waste ◽  
Morphological Changes ◽  
Deionized Water ◽  
Engineering Properties ◽  
Nuclear Waste Repository ◽  
Exchange Cation ◽  
Mineral Components ◽  
Waste Repository ◽  
Mineralogical Compositions

ABSTRACTFourteen Canadian clays and clay admixtures were subjected to simulated nuclear waste repository environments. The present work is concerned with the montmorillonite-dominant materials only. The montmorillonite-dominant samples showed significant leaching on interaction with deionized water. On heating the samples at 200°C for 500 hours, montmorillomites lost intermicellar water completely and acquired cusp-like to cylindrical morphologies. The loss of water and the morphological changes in montmorillonites significantly altered the engineering characteristics. Permeability, shrinkage limits, compactability and shear strength varied in response to the dominant exchange cation in the structure of montmorillonites and the presence of other mineral components in the materials. The synthetic granite water reacted with montmorillonites and led to changes in chemical and mineralogical compositions, crystalline state and engineering properties.

Modelling of thermal rock mass properties at the potential sites of a Swedish nuclear waste repository

2009 ◽  
Vol 46 (6) ◽  
pp. 1042-1054 ◽  
Author(s):  
Jan Sundberg ◽  
Pär-Erik Back ◽  
Rolf Christiansson ◽  
Harald Hökmark ◽  
Märta Ländell ◽  
...  
Keyword(s):  
Rock Mass ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Rock Mass Properties ◽  
Mass Properties ◽  
Waste Repository

An analytical solution of temperature in a nuclear waste repository

2021 ◽  
Vol 163 ◽  
pp. 108535
Author(s):  
Yao Xue ◽  
De'an Sun ◽  
Lei Wang
Keyword(s):  
Analytical Solution ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Waste Repository

Erratum: “A Review of Corrosion of Titanium Grade 7 and Other Titanium Alloys in Nuclear Waste Repository Environments” (Vol. 61, No. 10, p. 987–1,003)

CORROSION ◽  
2005 ◽  
Vol 61 (11) ◽  
pp. 1107-1107
Author(s):  
F. Hua ◽  
K. Mon ◽  
P. Pasupathi ◽  
G. Gordon ◽  
D. Shoesmith
Keyword(s):  
Titanium Alloys ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Waste Repository ◽  
Titanium Grade
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