Electrometallurgical Techniques for DOE Spent Fuel Treatment Status Report on Argonne National Laboratory's R & D Activity as of Fall 1998 (1999) / Chapter Skim
Currently Skimming:
E Committee Meeting at Argonne National Laboratory-East, October 26-27, 1998
E Committee Meeting at Argonne National Laboratory-East, October 26-27, 1998
Pages 71-80
The Chapter Skim interface presents what we've algorithmically identified as the most significant single chunk of text within every page in the chapter.
Select key terms on the right to highlight them within pages of the chapter.
From page 71... ...
M Goff Ceramic Waste Form Fission Product Release Modeling T
|
From page 72... ...
Significant accomplishments for driver treatment include eight assemblies treated in ~ month, 693 kg of low enriched uranium cast, cathode processor batch size increased from 12 to 17 kilograms, casting furnace batch size increased from 36 to 54 kg, and 468 kg of low enriched uranium shipped. Blanket treatment started in August 1998.
|
From page 73... ...
Planned near-term tests include the continued investigation of the uranium dissolution method to remove the dense uranium deposit from the cathode tubes, parametric tests with the ACM and 25-tn.-diameter HTERs, and parametric tests that will include effects of current density, anode basket spacing, separation between the anode baskets and the cathode tubes, separation between the scraper and the cathode tubes, and rotation speed of the anode Dive on the uranium throughput rate. Robert W
|
From page 74... ...
These data were submitted through DOE-EM, with a first submittal in July 1997 and a final submittal in May 1998. Qualification activities to be completed by the end of the demonstration project include completion of the waste form testing matrices, except for radioactive samples, and tests that last longer than ~ year.
|
From page 75... ...
Alloy samples that have been tested for up to 3 years in I-13 show minor surface tarnish, considerable scatter in data, and that normalized losses are small, i.e., that there are low corrosion rates. Other characterization tests include pulse flow immersion tests.
|
From page 76... ...
Current MWF corrosion testing includes immersion testing, electrochemical testing, and vapor hydration testing. Additional testing will include chloride contents up to 10,000 ppm, room temperature up to 90 C, pH between 5 and 10, various MWF alloy compositions, and crevice-corrosion tests.
|
From page 77... ...
Waste forms are being investigated with the full range of Pu levels. Advance fabrication of the ceramic waste form includes high-temperature, pressureless consolidation.
|
From page 78... ...
The tests, at 2000 and 20,000 my, verify pH independence. Tom Fanning, ANL-E, presented information on ceramic waste form radionuclide release modeling.
|
From page 79... ...
The salt-soluble fission products and the particulate fission products are then separated and made into a ceramic waste form, while uranium, transuranic elements, and noble-metal fission products are separated and sent to the electrorefiner. The focus of the oxide work is twofold.
|
From page 80... ...
of fission products in aluminum and in the salt. Thermodynamic calculations predict that the salt phase will contain active metal and rare-earth fission products, and the metal phase will contain uranium, plutonium, and noble-metal fission products.
|
Key Terms
This material may be derived from roughly machine-read images, and so is provided only to facilitate research.
More
information on Chapter Skim is available.