scholarly journals Leach Testing of Idaho Chemical Processing Plant Final Waste Forms

1982 ◽  
Vol 56 (2) ◽  
pp. 254-264 ◽  
Author(s):  
R. P. Schuman
Keyword(s):  
Processing Plant ◽  
Chemical Processing ◽  
Waste Forms

scholarly journals Hot Isostatic Press (Hip) Vitrification of Radwaste Concretes

1995 ◽  
Vol 412 ◽  
Author(s):  
Darryl D. Siemer ◽  
Barry E. Scheetz ◽  
Mary Lou Gougar
Keyword(s):  
Potential Application ◽  
Processing Plant ◽  
Chemical Processing ◽  
Waste Forms ◽  
Good Productivity

AbstractProperly prepared cementitious waste forms can be hot-isostatically-pressed into materials that exhibit performance equivalent to typical radwaste-type glasses. The HIPing conditions (temperature/pressure) required to “vitrify” these concretes are quite mild and therefore consistent with both safety and good productivity. This paper describes both the process and its products with reference to potential application to Idaho Chemical Processing Plant (ICPP) reprocessing wastes.

Stability of NZP Waste Forms and their Application To ICCP Waste

1984 ◽  
Vol 44 ◽  
Author(s):  
B. E. Scheetz ◽  
S. Komarneni ◽  
W. Fajun ◽  
L. J. Yang ◽  
M. Ollinen ◽  
...  
Keyword(s):  
Zirconium Phosphate ◽  
Processing Plant ◽  
Chemical Processing ◽  
Stability Studies ◽  
Waste Forms ◽  
Sodium Zirconium ◽  
Phosphate Phase ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Sodium Zirconium Phosphate

AbstractThe crystal structure of NaZr2(PO4)3, (NZP), contains three distinct crystallographic sites which between them can readily accommodate the majority of elements that are present in high level nuclear waste. The applicability of this host phase to the immobilization of mixed zirconia/alumina waste from the Idaho Chemical Processing Plant (ICPP) was demonstrated. A waste form consisting of CaF2, a number of NZP phases and F-apatite was prepared and the results of leach testing reported. Detailed stability studies of the host sodium zirconium phosphate phase were also conducted as a function of temperature, pH and time.

Glass-Ceramic Waste Forms for Immobilizing Plutonium

1996 ◽  
Vol 465 ◽  
Author(s):  
T. P. O'Holleran ◽  
S. G. Johnson ◽  
S. M. Frank ◽  
M. K. Meyer ◽  
M. Noy ◽  
...  
Keyword(s):  
Glass Ceramic ◽  
High Level Waste ◽  
Processing Plant ◽  
Chemical Processing ◽  
X Ray Diffraction ◽  
X Ray ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Diffraction Patterns ◽  
High Level

ABSTRACTResults are reported on several new glass and glass-ceramic waste formulations for plutonium disposition. The approach proposed involves employing existing calcined high level waste (HLW) present at the Idaho Chemical Processing Plant (ICPP) as an additive to: 1) aid in the formation of a durable waste form and 2) decrease the attractiveness level of the plutonium from a proliferation viewpoint. The plutonium, PuO2, loadings employed were 15 wt% (glass) and 17 wt% (glass-ceramic). Results in the form of x-ray diffraction patterns, microstructure and durability tests are presented on cerium surrogate and plutonium loaded waste forms using simulated calcined HLW and demonstrate that durable phases, zirconia and zirconolite, contain essentially all the plutonium.

Experimental Glass-Ceramic Products to Immobilize ICPP HLW

1987 ◽  
Vol 112 ◽  
Author(s):  
Roseanne S. Baker ◽  
Bruce A. Staples ◽  
Dieter A. Knecht ◽  
Julius R. Berreth
Keyword(s):  
Glass Ceramic ◽  
Hot Isostatic Pressing ◽  
Glass Ceramics ◽  
High Level Waste ◽  
Processing Plant ◽  
Chemical Processing ◽  
Stabilized Zirconia ◽  
Experimental Glass ◽  
Ceramic Glass ◽  
High Level

AbstractCandidate products are being evaluated to immobilize the routinely calcined waste at the Idaho Chemical Processing Plant (ICPP). A potential product with minimal volume for immobilizing ICPP high-level waste (HLW) for final disposal is a high-waste-loading and high-density glass-ceramic. Glass-ceramics are formed by Hot Isostatic Pressing (HIPing) the HLW with selected additives, such as SiO2, B2O3, Li2O, Na2O, and Y2O3. Glass-ceramic products have been formed with calcine loa ings up to 80 wt% and densities up to 3.4 g/cm3. Crystalline phases observed in the glass-ceramic products include calcium fluoride, monoclinic and cubic zirconia, calcium- and yttrium-stabilized zirconia, and zircon. An interstitial amorphous phase also exists consisting of the oxides of silicon, aluminum, boron, and alkalis. The glass-ceramic waste forms give leach rates comparable to simulated HLW glass products.

Characteristics of Preliminary Waste Forms for Icpp Low Activity Waste (Law) Fractions after Radionuclide Separations

1995 ◽  
Vol 412 ◽  
Author(s):  
Krishna Vinjamuri
Keyword(s):  
Structural Parameters ◽  
Chemical Durability ◽  
Liquid Sodium ◽  
Processing Plant ◽  
Chemical Processing ◽  
Waste Streams ◽  
Standard Glass ◽  
Radioactive Sodium ◽  
High Level ◽  
Low Activity

AbstractCurrently, at the Idaho Chemical Processing Plant (ICPP) there are about 6800 m3 of liquid sodium-bearing and liquid high-level wastes (HLW), and 3800 m3 of solid calcined HLW. One of the waste processing options under consideration includes separation of the HLW into high activity and low activity (LAW) wastes, followed by immobilization. Preliminary glasses were synthesized for the sodium-bearing, alumina-bearing, and the zirconia-bearing LAW fractions after radionuclide separations. The glasses were formed by crucible melting of a mixture of reagent chemicals representative of the LAW waste streams and frit additives at 1200 °C for 5 hours, followed by overnight annealing at 550 °C and furnace cooling of the melt. These glasses were characterized for density, elastic property, viscosity, chemical durability, structural parameters, and glass phase separation. The results are compared with that of the Hanford's standard glass ARM-i, Savannah River's benchmark glass EA, and the ICPP's grout waste form prepared using the simulated non-radioactive sodium-bearing waste fraction.

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