Characterization of and Waste Acceptance Radionuclides to be Reported for the Second Macro-Batch of High-Level Waste Sludge Being Vitrified in the DWPF Melter

1999 ◽  
Vol 608 ◽  
Author(s):  
T.L. Fellinger ◽  
N.E. Bibler ◽  
W.T. Boyce ◽  
J.J. Olson
Keyword(s):  
High Level Waste ◽  
Waste Sludge ◽  
High Level

Demonstration of the defense waste processing facility vitrification process for tank 42 radioactive sludge – glass preparation and characterization

1999 ◽  
Vol 556 ◽  
Author(s):  
Ned E. Bibler ◽  
Terri L. Fellinger ◽  
Kathryn M. Marshall ◽  
Charles L. Crawford ◽  
A. D. Cozzi ◽  
...  
Keyword(s):  
High Level Waste ◽  
Waste Processing ◽  
Savannah River ◽  
Glass Forming ◽  
Waste Sludge ◽  
Process Flowsheet ◽  
Processing Facility ◽  
High Level ◽  
River Site

AbstractThe Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is currently processing and immobilizing the radioactive high level waste sludge at SRS into a durable borosilicate glass for final geological disposal. The DWPF has recently finished processing the first radioactive sludge batch, and is ready for the second batch ofradioactive sludge. The second batch is primarily sludge from Tank 42. Before processing this batch in the DWPF, the DWPF process flowsheet has to be demonstrated with a sample of Tank 42 sludge to ensure that an acceptable melter feed and glass can be made. This demonstration was recently completed in the Shielded Cells Facility at SRS. An earlier paper in these proceedings described the sludge composition and processes necessary for producing an acceptable melter feed [1]. This paper describes the preparation and characterization of the glass from that demonstration. Results substantiate that Tank 42 sludge after mixing with the proper amount of glass forming frit (Frit 200) can be processed to make an acceptable glass.

Preparation and characterization of vitrified glass matrix for high level waste from MOX fuel processing

2007 ◽  
Vol 353 (52-54) ◽  
pp. 4647-4653 ◽  
Author(s):  
V.S. Yalmali ◽  
D.S. Deshingkar ◽  
P.K. Wattal ◽  
S.R. Bharadwaj
Keyword(s):  
Glass Matrix ◽  
High Level Waste ◽  
Fuel Processing ◽  
Mox Fuel ◽  
High Level

Study of Melted Synroc Doped with Simulated High-Level Waste

1996 ◽  
Vol 465 ◽  
Author(s):  
I. A. Sobolev ◽  
S. V. Stefanovsky ◽  
S. V. Ioudintsev ◽  
B. S. Nikonov ◽  
B. I. Omelianenko ◽  
...  
Keyword(s):  
Bulk Composition ◽  
Barometric Pressure ◽  
High Level Waste ◽  
Savannah River ◽  
Savannah River Plant ◽  
High Level ◽  
A Minor ◽  
Simulated High Level Waste ◽  
Additional Phase

ABSTRACTPreparation and characterization of inductively-melted Synroc containing 20 wt% simulated plant “Mayak” reprocessing waste were performed. The sample bulk composition was as follows, (in wt.%): 55.4 TiO2; 15.8 ZrO2; 7.5 CaO; 7.4 BaO; 4.3 Al2O3 2.0 MnO; 1.8 SiO2; 0.7 Na2O; 1.9 K2O, 0.5 Ce2O3; 1.0 UO2; 0.9 NiO; 0.6 Cr2O3, and 0.2 FeO. The sample was produced by melting in air at 1550–1600 °C under barometric pressure. It is composed of a few crystalline phases and a minor glass phase. Most of the phases (hollandite, zirconolite, perovskite and rutile) are similar to the analogous phases found in the other Synroc formulations. An additional phase with average composition, wt.%: 59.8 TiO2; 15.6 CaO; 7.0 UO2; 5.6 ZrO2; 4.7 MnO; 4.1 Ce2O3, and 1.8 Al2O3 was found. Some elements (Ba, Si, Ni, K, Na, Fe) were present in the phase in negligible quantities. Its formula (Ca2.65U0.3Ce0.2)(Ti7.3Mn0.6Zr0.4Al0.3)O20.0 is rather close to a rare mineral uhligite - Ca3(Ti,Zr,Al)9O20. Another possible counterpart of the phase is murataite-like mineral previously described in tailored ceramic designed for Savannah River Plant wastes fixation. This phase as well as zirconolite are the major host for U in the sample Preliminary data on the material leachability in water at 350 °C and 50 MPa have been obtained Uranium contents in the solution were about 1 ppb and close to the uranium dioxide solubility in deionized water under the same P-T conditions.

Characterization of high level waste for minor actinides by chemical separation and alpha spectrometry

2011 ◽  
Vol 294 (1) ◽  
pp. 149-153 ◽  
Author(s):  
M. S. Murali ◽  
A. Bhattacharayya ◽  
D. R. Raut ◽  
A. S. Kar ◽  
B. S. Tomar ◽  
...  
Keyword(s):  
Alpha Spectrometry ◽  
Chemical Separation ◽  
High Level Waste ◽  
Minor Actinides ◽  
High Level
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