An alternative host matrix based on iron phosphate glasses for the vitrification of specialized nuclear waste forms. 1998 annual progress report

Lead-iron phosphate glasses have recently been proposed as a new primary disposal medium for both commercial nuclear reactor wastes and some types of high-level radioactive U.S. defense wastes [1–41. The initial work on the characterization of lead-iron phosphate nuclear waste glasses, hereafter named phosphate glasses, concentrated on the preparation, thermal properties, and devitrification behavior (both during and after preparation) of these glasses. Aqueous corrosion rates were measured at 90°C in distilled water, acidic and basic solutions, low eH distilled water, and in the “reference’ natural ground water appropriate to disposal in a tuffaceous formation (i.e., J-13 well water [5]). The results of these initial investigations were extremely encouraging and indicated that homogeneous, highly leach resistant (at 90° C) phosphate glasses loaded with either commercial or high-level U.S. defense wastes could be prepared at relatively low temperatures (process temp.:≤ 1050°C). The chemical stability of the phosphate glasses was found to be primarily due to the stabilizing effect of iron on the structure of lead phosphate glass. This effect is illustrated in Fig. 1 where the leachate conductivity at 90°C is plotted versus time for phosphate glasses with varying iron concentrations. The addition of 9 wt.% iron oxide to lead metaphosphate glass [Pb(PO3)2] increases the chemical durability of the glass in water by a factor of about 104. The tendency of pure lead phosphate glasses to crystallize is also greatly suppressed by the addition of iron oxide [3,4]. Lead metaphosphate glass can be completely crystallized by heating the glass in air at 30O°C for several hours. Lead-iron phosphate glasses, however, can be heated in air for several hundred hours at a temperature as high as 500°C without exhibiting any evidence of crystallization.

Thermal characterization of iron phosphate glasses for nuclear waste disposal

Optical Materials ◽

10.1016/j.optmat.2011.03.050 ◽

2011 ◽

Vol 33 (12) ◽

pp. 1975-1979 ◽

Cited By ~ 15

Author(s):

A.S. Pinheiro ◽

Z.M. da Costa ◽

M.J.V. Bell ◽

V. Anjos ◽

N.O. Dantas ◽

...

Keyword(s):

Nuclear Waste ◽

Waste Disposal ◽

Thermal Characterization ◽

Iron Phosphate ◽

Nuclear Waste Disposal ◽

Phosphate Glasses ◽

Iron Phosphate Glasses

05/00800 Vitrification of high chrome oxide nuclear waste in iron phosphate glasses

Fuel and Energy Abstracts ◽

10.1016/s0140-6701(05)80803-3 ◽

2005 ◽

Vol 46 (2) ◽

pp. 117

Keyword(s):

Nuclear Waste ◽

Iron Phosphate ◽

Phosphate Glasses ◽

Chrome Oxide ◽

Iron Phosphate Glasses

Vitrification of high chrome oxide nuclear waste in iron phosphate glasses

Journal of Nuclear Materials ◽

10.1016/j.jnucmat.2004.01.021 ◽

2004 ◽

Vol 327 (1) ◽

pp. 46-57 ◽

Cited By ~ 39

Author(s):

Wenhai Huang ◽

Delbert E. Day ◽

Chandra S. Ray ◽

Cheol-Woon Kim ◽

Andrea Mogus-Milankovic

Keyword(s):

Nuclear Waste ◽

Iron Phosphate ◽

Phosphate Glasses ◽

Chrome Oxide ◽

Iron Phosphate Glasses

Sodium–aluminum–iron phosphate glasses as legacy high level waste forms

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2016.01.022 ◽

2017 ◽

Vol 94 ◽

pp. 229-234 ◽

Cited By ~ 10

Author(s):

S.V. Stefanovsky ◽

O.I. Stefanovsky ◽

M.B. Remizov ◽

P.V. Kozlov ◽

E.A. Belanova ◽

...

Keyword(s):

Iron Phosphate ◽

Phosphate Glasses ◽

High Level Waste ◽

Waste Forms ◽

Aluminum Iron ◽

High Level ◽

Iron Phosphate Glasses

Iron – Phosphate Glass (IPG) Waste Forms Produced using Induction Melter with Cold Crucible

MRS Proceedings ◽

10.1557/proc-807-187 ◽

2003 ◽

Vol 807 ◽

Cited By ~ 5

Author(s):

A.S Aloy ◽

R. A. Soshnikov ◽

A. V. Trofimenko ◽

D. Gombert ◽

D. Day ◽

...

Keyword(s):

Iron Phosphate ◽

Major Elements ◽

Phosphate Glasses ◽

Cold Crucible ◽

Borosilicate Glasses ◽

X Ray Diffraction ◽

High Sodium ◽

Waste Forms ◽

Waste Loading ◽

Iron Phosphate Glasses

ABSTRACTA simulated sodium bearing waste (SBW), which represented a type of high sodium and sulfate waste, was successfully vitrified in iron phosphate glasses (IPG), at a maximum waste loading of 40 wt%, using a cold crucible induction melter (CCIM). Scanning electron microscopy (SEM) and X-ray diffraction (XRD) showed that all of the IPG waste forms did not contain sulfate salt segregation or crystalline phases. The calculated composition and the average analytical composition obtained by Electron Probe Microanalysis (EPMA) were in good agreement. The major elements were uniformly distributed throughout the samples. The chemical durability of the IPG waste forms containing 40wt% SBW was evaluated by the product consistency test (PCT) and met current DOE requirements. IPG waste forms were melted at a relatively low temperature and for short times compared to borosilicate glasses. These advantages, combined with those of a significantly higher waste loading and the feasibility for CCIM melting, offer a considerable savings in time, energy, and cost for vitrifying this high sodium and sulfate waste.

The Formation and Modeling of Colloids from the Corrosion of Nuclear Waste Forms

10.1557/proc-1124-q11-01 ◽

2008 ◽

Author(s):

Edgar Buck ◽

Rick S. Wittman

Keyword(s):

Nuclear Waste ◽

Waste Forms ◽

Nuclear Waste Forms