72 results on '"Ebert, W. L."'
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2. Corrosion rates measured under potentiostatic conditions to represent performance of a cermet nuclear waste form
3. Effects of Mo additions on the potentiostatic corrosion behaviour of multiphase 316L SS-based alloys
4. Impact of added Inconel and stainless steel on zirconium-based alloys for nuclear waste applications
5. The Experimental Hydration of Obsidian as a Function of Relative Humidity and Temperature
6. Application of the TSPA Glass Degradation Model to Non-Conforming Waste Forms
7. Designing Advanced Ceramic Waste Forms for Electrochemical Processing Salt Waste
8. Long-Term Corrosion Tests with Hanford Glasses
9. Test plan for formulation and evaluation of grouted waste forms with shine process wastes
10. Closed Fuel Cycle Waste Treatment Strategy
11. Accounting For Corrosion Of Hlw Glasses By Humid Air In TSPA
12. Accounting for EBR-II Metallic Waste Form Degradation in TSPA
13. Corrosion of Glass-Bonded Sodalite as a Function of pH and Temperature
14. Comparison of the results of short-term static tests and single-pass flow-through tests with LRM glass.
15. Yucca Mountain project : FY 2006 annual report for waste form testingactivities.
16. Corrosion testing of a plutonium-loaded lanthanide borosilicate glass made with Frit B.
17. Interlaboratory study of the reproducibility of the single-pass flow-through test method : measuring the dissolution rate of LRM glass at 70 {sup {degree}}C and pH 10.
18. Effect of molybdenum additions on the microstructures and corrosion behaviours of 316L stainless steel-based alloys
19. Mechanism of iodine release from iodoapatite in aqueous solution
20. YUCCA Mountain project.
21. Static leach tests with the EBR-II metallic waste form.
22. Status of ceramic waste form degradation and radionuclide release modeling.
23. Corrosion tests to determine temperature and pH dependencies of the dissolution rates of sodalite, binder glass, and ceramic waste form.
24. Corrosion tests with uranium- and plutonium-loaded ceramic waste forms.
25. Tests with ceramic waste form materials made by pressureless consolidation.
26. Development of a method for monitoring the consistency of glass-bonded sodalite waste forms.
27. Hanford Immobilized LAW Product Acceptance: Initial Tanks Focus Area Testing Data Package
28. Round-robin testing of a reference glass for low-activity waste forms
29. A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford
30. A two satellite technique for measuring atmospheric surface pressure
31. Monitoring Consistency of the Ceramic Waste Form
32. Kinematics, Dynamics, and Estimation of Rigid-Body Motion Using Euler Parameters (Quaternions)
33. Comparison of the Corrosion Behavior of Tank 51 Sludge-Based Glass and a Nonradioactive Homologue Glass
34. Dissolution Rates of DWPF Glasses from Long-Term PCT
35. Simulation of Natural Corrosion by Vapor Hydration Test: Seven-Year Results
36. Secondary Phase Formation and the Microstructural Evolution of Surface Layers During Vapor Phase Alteration of the French Son68 Nuclear Waste Glass at 200 °C
37. The Release of Technetium from Defense Waste Processing Facility Glasses
38. The Reaction of SRL 202 Glass in J-13 and DIW
39. High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics
40. Accelerated Glass Reaction Under PCT Conditions
41. Modeling Surface Area to Volume Effects on Borosilicate Glass Dissolution
42. The Role of Surface Layers in Glass Leaching Performance
43. An interlaboratory study of a standard glass for acceptance testing of low-activity waste glass
44. Analytical electron microscopy study of surface layers formed on the French SON68 nuclear waste glass during vapor hydration at 200 C
45. Kinematics, Dynamics, and Estimation of Rigid-Body Motion Using Euler Parameters (Quaternions)
46. The Reaction of Synthetic Nuclear Waste Glass in Steam and Hydrothernal Solution
47. Modeling Surface Area to Volume Effects on Borosilicate Glass Dissolution.
48. Accelerated Glass Reaction Under PCT Conditions.
49. High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics.
50. The Reaction of SRL 202 Glass in J-13 and DIW.
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