Yucca Mountain Project - Argonne National Laboratory Annual Progress Report, FY 1994
John K. Bates,Jeffrey A. Fortner,Patricia A. Finn,David J. Wronkiewicz,J.C. Hoh,J. W. Emery,Edgar C. Buck,Stephen F. Wolf +7 more
- 01 Feb 1995
TL;DR: The work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994 is described in this paper.
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Abstract: This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form.
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Figures
Fig. 18. SEM Photomicrographs for the Bottom Surface of UO2 Pellet after Eight Years of Reaction: (a) Schoepite Crystals Showing Evidence for Dissolution Pitting, 
Table 13. Maximum Fraction (%) for Unsaturated High Drip-Rate versus Saturated Tests 
Table 12. Average Unprecipitated Fractions (%) for Unsaturated High Drip-Rate versus Saturated Tests 
Fig. 7. EDS Spectra from Analytical Transmission Electron Microscopy Study of N3 Series Colloids: (a) Clay Material with Evidence of Uranium Silicate Formation and (b) Clay Material with Evidence of Brockite (a Ca-Th-P Bearing Mineral) Formation (inset) 
Table 3. N3 Test Sample Identification 
Fig. 4. Cumulative Mass Release of (a) Sodium, (b) Silicon, (c) Potassium, and (d) Calcium from the N3 Test Series, Corrected for EJ-13 Injection Contributions, through
Citations
Long-Term Results from Unsaturated Durability Testing of Actinide-Doped DWPF and WVDP Waste Glasses
Jeffrey A. Fortner,John K. Bates +1 more
TL;DR: In this paper, the results from durability drip tests designed to simulate the unsaturated conditions in the proposed Yucca Mountain Repository are reported for two actinide-doped glasses used as model waste forms.
14
Long-term kinetic effects and colloid formations in dissolution of LWR spent fuels
T.M. Ahn
- 01 Nov 1996
TL;DR: In this paper, the authors evaluated continuous dissolution and colloid formation during spent-fuel performance under repository conditions in high-level waste disposal and found that the diffusion limits of various species involved may retard dissolution significantly.
Direct Investigations Of The Immobilization Of Radionuclides In The Alteration Phases Of Spent Nuclear Fuel
Peter C. Burns,Robert J. Finch,David J. Wronkiewicz +2 more
- 31 Dec 2003
TL;DR: In this paper, the incorporation of radionuclides into U(VI) alteration products by synthesizing uranyl phases doped with radions, appropriate surrogate elements, or non-radioactive isotopes was investigated.
Spent fuel`s behavior under dynamic drip tests
P.A. Finn,E.C. Buck,J.C. Hoh,J.K. Bates +3 more
- 01 Dec 1995
TL;DR: In this paper, Colloidal species containing americium and plutonium have been found in the leachate of spent nuclear fuel, which suggests that colloidal transport of radionuclides should be included in the performance assessment of a potential repository.
Long-term test results from a West Valley actinide-doped reference glass
J.A. Fortner,T.J. Gerding,J.K. Bates +2 more
- 01 Jul 1995
TL;DR: The results from drip tests designed to simulate unsaturated conditions in the proposed Yucca Mountain Repository are reported for an actinide-doped glass (reference glass ATM-10) used as a model waste form as discussed by the authors.
References
Spent fuel corrosion and dissolution
R.S. Forsyth,L.O. Werme +1 more
TL;DR: In this article, the current status of the Swedish program for the study of the corrosion of spent fuel in bicarbonate groundwaters is presented and compared with the data base accumulated over the past ten years Release of uranium and other actinides was solubility-controlled under the semistatic type of experiments performed.
140
Characterization of spent fuel approved testing material: ATM-103
R.J. Guenther,D.E. Blahnik,T.K. Campbell,U.P. Jenquin,J.E. Mendel,L.E. Thomas,C.K. Thornhill +6 more
- 01 Apr 1988
TL;DR: The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1 as discussed by the authors.
Oxidative alteration of uraninite at the Nopal I deposit, Mexico: Possible contaminant transport and source term constraints for the proposed repository at Yucca Mountain
TL;DR: The Nopal I uranium deposit at Pena Blanca, Mexico is studied as a natural analog of the proposed high-level nuclear waste repository at Yucca Mountain this article, and the spatial distribution of uranium and measurements of {sup 238}U decay-series isotopes indicate secular equilibrium, which suggests undetectable U transport under present conditions.
18
Dissolution of used CANDU fuel at various temperatures and redox conditions
TL;DR: In this article, electron microscopy and X-ray diffraction techniques were used to examine used UO/sub 2/ fuel exposed to air-saturated water at 25/sup 0/C for eight years.
17
Parametric Effects on Glass Reaction in the Unsaturated Test Method
Alan B. Woodland,John K. Bates,Thomas J. Gerding +2 more
- 01 Dec 1991
TL;DR: In this article, the results from five separate sets of parametric experiments are presented wherein test parameters ranging from water contact volume to sensitization of metal in contact with the glass were examined, and the most significant effect was observed when the volume of water, as controlled by the water inject volume and interval period, was such to allow exfoliation of reacted glass to occur.