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.

Polyphase Ceramic and Glass-Ceramic forms for Immobilizing ICPP High-Level Nuclear Waste

1983 ◽  
Vol 26 ◽  
Author(s):  
Alan B. Harker ◽  
John F. Flintoff
Keyword(s):  
Glass Ceramic ◽  
Glass Matrix ◽  
Hot Isostatic Pressing ◽  
Glass Frit ◽  
Processing Plant ◽  
Chemical Processing ◽  
Chemical Additives ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Consolidation Temperature

ABSTRACTPolyphase ceramic and glass-ceramic forms have been consolidated from simulated Idaho Chemical Processing Plant wastes by hot isostatic pressing calcined waste and chemical additives at 1000°C or less. The ceramic forms can contain over 70 wt% waste with densities ranging from 3.5 to 3.85 g/cm3, depending upon the formulation. Major phases are CaF2, CaZrTi2O7, CaTiO3, monoclinic ZrO2, and amorphous intergranular material. The relative fraction of the phases is a function of the chemical additives (TiO2, CaO, and Si02) and consolidation temperature. Zirconolite, the major actinide host, makes the ceramic forms extremely leach resistant for the actinide simulant U238. The amorphous phase controls the leach performance for Sr and Cs which is improved by the addition of SiO2. Glass-ceramic forms were also consolidated by HIP at waste loadings of 30 to 70 wt% with densities of 2.73 to 3.1 g/cm3 using Exxon 127 borosilicate glass frit. The glass-ceramic forms contain crystalline CaF2, Al2O3, and ZrSiO4 (zircon) in a glass matrix. Natural mineral zircon is a stable host for 4+ valent actinides.

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.

Study of Glass-Ceramic Waste Forms

1997 ◽  
Vol 506 ◽  
Author(s):  
S.V. Stefanovsky ◽  
S.V. Ioudintsev ◽  
B.S. Nikonov ◽  
B.I. Omelianenko ◽  
T.N. Lashtchenova
Keyword(s):  
Glass Ceramic ◽  
Glass Composition ◽  
Glass Ceramics ◽  
High Level Waste ◽  
Matrix Glass ◽  
Crystalline Phases ◽  
Cell Parameters ◽  
The Matrix ◽  
High Level ◽  
Similar Unit

ABSTRACTSince the early of the 1990s the method of inductive melting in a cold crucible (IMCC) has been applied at SIA “Radon” for production of various wasteforms, including glasses and Synroc-type ceramics. Sphene-based glass-ceramics composed of glass and crystalline phases were considered as appropriate wasteform for High Level Waste immobilisation. Investigation of two glass-ceramic specimens prepared with the IMCC has been performed using optical microscopy, XRD, SEM/EDS, and TEM methods. The samples produced consist of vitreous and crystalline phases. The vitreous phase consists of two varieties of glass formed by the immiscibility of the initial melt onto two separate liquids. One of the glasses is observed as spherical microinclusions in the matrix glass. The glass of the microspheres are differed from the matrix glass composition by higher contents of Ca, Ti, Ce, Sr, Zr (or Cr), while the matrix glass contains higher amounts of Si, Al, and alkalies. The crystalline phases with sphene- and perrierite-like structures have been also occurred. Their total quantity reaches up to 50 vol.%. The synthetic perrierite has similar unit-cell parameters with its natural mineral analogs with the only exception in two-fold value of c dimension. Zr, Ce, and Sr are incorporated into synthetic sphene and perrierite, while Cs is hosted by the glass phases.

scholarly journals Study of The Effect of TiO2 Addition On The Crystalline Phases, Structure and Chemical Durability of a Nuclear Glass Ceramic

2021 ◽  
Author(s):  
Rafika SOUAG ◽  
Nour elhayet KAMEL ◽  
Dalila Moudir ◽  
Yasmina MOUHEB ◽  
Fayrouz Aouchiche
Keyword(s):  
Glass Ceramic ◽  
Glass Ceramics ◽  
Ceramic Materials ◽  
Chemical Durability ◽  
Aluminosilicate Glass ◽  
High Level Waste ◽  
X Ray Diffraction ◽  
Complex Chemical Composition ◽  
High Level ◽  
Selection Of

Abstract This study focused on the effect of TiO 2 addition on the crystallines phases’ formation, structure and chemical durability of a nuclear glass ceramic constituted by an aluminosilicate glass in the system: SiO2-Al2O3-CaO-MgO-ZrO2-TiO2 . The materials with four contents of TiO2 , ranging from 4.11 to 7.11 wt.%, are synthesized by a discontinuous method,. For the whole of materials, X-ray diffraction analysis allow identifying an aluminosilicate belonging to pyroxenes silicates family as a main phase, powelite and calzirtite. Both SEM and DTAanalyses confirmed these results. The materials FTIR analysis reveals the glass ceramics complex chemical composition. MCC1 and MCC2 tests, performed on selected glass ceramic materials, indicate that the materials with 4.11 and 5.11 wt.% TiO2 are the most durable against Si, Al, Mg and Ce elements release, in MCC2 test; The results make conclusions valuable on the selection of such glass ceramics as candidate for the disposal of high-level waste.

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.

Phase composition and elemental partitioning in glass–ceramics containing high-Na/Al high level waste

2012 ◽  
Vol 424 (1-3) ◽  
pp. 75-81 ◽  
Author(s):  
S.V. Stefanovsky ◽  
A.N. Sorokaletova ◽  
B.S. Nikonov
Keyword(s):  
Phase Composition ◽  
Glass Ceramics ◽  
High Level Waste ◽  
High Level

Relevant properties of ceramics for immobilization of high level waste. An example: A glass-ceramic through a sol-gel route

1987 ◽  
Vol 17 (5) ◽  
pp. 475-484 ◽  
Author(s):  
A. Salomoni ◽  
E.H. Toscano ◽  
A. Caneiro ◽  
A. Montenero ◽  
G. Ondracek
Keyword(s):  
Glass Ceramic ◽  
Sol Gel ◽  
High Level Waste ◽  
High Level
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