Provided herein is a process for removal of 99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO.sub.3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool(msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of 99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified 99Tc bearing waste.

A metal oxide barrier and a connecting method for solving the problems in which sectors of an existing cold crucible are connected by means of a mica plate and the mica plate is damaged due to arcing and the like and in which the sectors are strongly connected by means of the mica plate and thus are difficult to replace and maintain. A cold crucible, comprising a metal oxide barrier, according to the present invention can prevent arcing, enables reduction of damage on the edge part of a water cooling sector due to a molten material and thus enhances durability. Moreover, the metal oxide barrier can easily be replaced compared to an existing mica plate and thus enables easy maintenance and repair.

A method for vitrifying waste to prevent the formation of molybdate secondary phases includes forming a feed mixture that includes the waste, a source of vanadium, and at least one of glass frit or glass forming chemicals and vitrifying the feed mixture in a melter to produce a glass product that includes the waste.

Embodiments disclosed herein include methods and systems for melting or augmenting a melt rate of material in a melter using electromagnetic radiation with a frequency between 0.9 GHz and 10 GHz. In some examples, a power and/or frequency of radiation used may be selected so as to control a temperature of a cold cap in the melter while maintaining emissions from the melter below a threshold level. In this manner, examples described herein may provide for efficient and safe melting and vitrification of radioactive wastes.

The present invention provides solidified radioactive waste into which a titanium-containing adsorbent having a radioactive element adsorbed thereto is vitrified, the solidified radioactive waste being capable of confining a large amount of the titanium-containing adsorbent having a radioactive element adsorbed thereto, and furthermore elution of the radioactive element from the vitrified waste being suppressed. A method for producing solidified radioactive waste of the present invention is characterized by including heat-melting a mixture that includes a titanium-containing adsorbent having a radioactive element adsorbed thereto, a SiO.sub.2 source, and an M.sub.2O source (M represents an alkali metal element) to form vitrified waste, and the titanium-containing adsorbent is preferably one or two or more selected from silicotitanate, an alkali nonatitanate, and titanium hydroxide.

Disclosed herein are systems, methods, processes, and apparatuses for treating radioactive waste, through systems designed to bind and dry radioactive media and to mechanical devices and techniques that are utilized for removal of granular media from confined spaces (vessels and tanks). In some of its various embodiments, the system processes spent ion exchange media for long-term storage.

The method according to the invention enables a facility having a rather reduced dimension, for incinerating to be used, melting and vitrifying mixed waste (30) introduced into a reactor (10), by means of a basket (18) in turn passing through an air lock (12). Plasma torches (14) burn all waste (30) contained in the basket (18). The waste is then lowered in a melting bath of a furnace (20) with an inductor (24) including a crucible-forming container (23). A combustion gas treatment train completes the facility. The furnace (20) can be dismantled, after a series of treatments of several baskets (18) of waste (30) for disassembling the crucible-forming container (23) from the furnace (20). Application in treating different radiologically contaminated and/or toxic mixed waste.

The invention relates to a method for producing a solid nanocomposite material comprising nanoparticles of a metal coordination polymer with ligands CN, said nanoparticles satisfying the formula [Alk.sup.+.sub.x]M.sup.n+[M(CN).sub.m].sup.z? where Alk is an alkali metal, x is 1 or 2, M is a transition metal, n is 2 or 3, M is a transition metal, m is 6 or 8, and z is 3 or 4; said M.sup.n+ cations of the coordination polymer being bound by an organometallic bond or a coordination bond to an organic group R2 of an organic graft, and said organic graft furthermore being chemically attached, preferably by a covalent bond, to at least one surface of a solid support, by reaction of a group R1 of said graft with said surface.

The present invention relates to a volume reduction treatment method of a spent uranium catalyst. According to the volume reduction treatment method of a spent uranium catalyst of the present invention, the disposal cost of the spent uranium catalyst can be reduced and the utilization of the repository can be improved since the method can significantly reduce the volume of the final disposal waste of the spent uranium catalyst.

The invention relates to a smoothing tool (3) configured for smoothing glass frit in a radioactive environment, in an induction-melting cold crucible. Smoothing tool (3) comprising a rod (30), a grid (50) configured to be in contact with glass frit (7) to be smoothed, and at least one vibrator (37, 55, 56) configured to make the grid (50) vibrate. The grid (50) is mechanically connected to the rod (30).