Initial Results for the Experimental Evaluation of a Nuclear Waste Repository Source Term Model

1985 ◽  
Vol 69 (1) ◽  
pp. 114-118 ◽  
Author(s):  
B. P. McGrail ◽  
L. A. Chick ◽  
G. L. McVay
Keyword(s):  
Nuclear Waste ◽  
Experimental Evaluation ◽  
Source Term ◽  
Nuclear Waste Repository ◽  
Term Model ◽  
Waste Repository ◽  
Source Term Model ◽  
Initial Results

The Solubility Limited Source Term for Cement - Conditioned Wastes: A Status Report

1999 ◽  
Vol 556 ◽  
Author(s):  
F. P. Glasser
Keyword(s):  
Performance Assessment ◽  
Nuclear Waste ◽  
Thermodynamic Functions ◽  
Experimental Work ◽  
Source Term ◽  
Status Report ◽  
Nuclear Waste Repository ◽  
Nickel Chromium ◽  
Quantitative Performance ◽  
Waste Repository

AbstactAn important function of the cement backfill in a nuclear waste repository is to react with aqueous waste species and reduce their solubility. However, to quantify backfill performance it is first necessary to prove the existence and establish the nature of the chemical solubility controls. This can be done by characterising the solubility-limiting phases, determining their solubility and thermodynamic functions, and assessing their stability and persistence and solubility during backfill degradation. Much of the necessary data must be acquired experimentally. The title paper describes briefly the progresss of experimental work on selected species including nickel, chromium(III,VI), tin(IV) molybdenum(VI), uranium(VI), Ce(III,IV), thorium, actinide simulants (III, IV) and chloride. Data needs are assessed and although much experimental work remains to be done, methodologies have been developed which will expedite progress. The expectation of a more quantitative performance assessment of cement barriers is, therefore, attainable.

scholarly journals The Effect of Bacillus sp.ores on the Actinide Source Term at the WIPP Nuclear Waste Repository

2020 ◽  
Author(s):  
Juliet Swanson ◽  
Cindi Hazelton ◽  
Adrianne Navarrette ◽  
Michael Richmann ◽  
Floyd Stanley
Keyword(s):  
Nuclear Waste ◽  
Source Term ◽  
Nuclear Waste Repository ◽  
Waste Repository

Vegetation-Derived Insights on the Mobilization and Potential:Transport of Radionuclides from the Nopal I Natural Analog Site, Mexico

1999 ◽  
Vol 556 ◽  
Author(s):  
Bret W. Leslie ◽  
David A. Pickett ◽  
English C. Pearcy
Keyword(s):  
Source Term ◽  
Activity Ratio ◽  
Decay Chain ◽  
Yucca Mountain ◽  
Nuclear Waste Repository ◽  
Natural Analog ◽  
Ore Body ◽  
Term Model ◽  
High Level ◽  
Source Term Model

AbstractThe Nopal I uranium (U) deposit, Peñia Blanca, Mexico is a source term and contaminant transport natural analog to the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. In an attempt to characterize the mobilization and potential transport of adionuclides in the unsaturated zone at the Nopal I deposit, vegetation growing on ore piles was analyzed for 238U, 235U, and 232Th decay-series isotopes. Specimens of Phacelia robusta growing on highgrade piles of U ore were collected and analyzed by alpha autoradiography, and by alpha and gamma spectrometry. Activities for U, thorium (Th), and radium (Ra) isotopes (Bq/kg dried plant) were 300, 1000, and 7000 for 238U, 230Th, and 226Ra, respectively. The 226Ra activities in these specimens are among the highest ever measured for plants; furthermore, the plant-to-soil 226Ra concentration ratio is higher than expected. These results demonstrate the large mobility and bio-availability of Ra in the Nopal I environment, and support previous indications of recent loss of 226Ra from the ore body. Comparison between the activities of 238U and 232Th decay-chain Th isotopes in the plants and in the ore substrate indicate that relative mobilization into pore solutions of 228Th > 230Th > 232Th, in a ratio of about 50 – 25:4:1, respectively. The similarity of the plant's 234U/238U activity ratio (˜1.2) to that of a caliche deposit that formed adjacent to the Nopal ore body around 54 ka suggests the 234U/238U activity ratio of U released from the ore is approximately 1.2. The U and 236Ra isotope activities of the plants and ore substrate, and solubility considerations, are used to assess a source term model of the potential Yucca Mountain repository. These results suggest the use of a natural analog source term model in performance assessments may be non-conservative.

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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