Abstract: A process suitable for producing curie quantities of quite pure Sr-82,85 is given. After a Mo target is irradiated with energetic protons having energies greater than about 200 MeV, thus producing a large number of radioactive species, the particular species of Sr-82,85 are substantially separated from the other products by a 6-step process. The process comprises dissolution of the target in H.sub.2 O.sub.2, followed by use of several ion exchange resins, extraction with an organophosphorus compound, and several adjustments of pH values. Other embodiments include processes for producing relatively pure long-lived Rb isotopes, Y-88, and Zr-88.

Abstract: After dissolving irradiated nuclear fuel in a nitric acid medium, the vapor produced by this dissolution and consisting of water, nitrogen oxides and iodine is passed into a condenser, then into a column for the absorption of the nitrous vapor in which is formed recombined nitric acid containing iodine and nitrous ions, the iodine contained in the recombined acid being then separated-out. The nitrous ions present in the recombined acid have a favorable influence on the important first stage of that separation.

Abstract: A solution of potassium-38 suitable for use as a radiopharmaceutical and a method for its production. Argon is irradiated with protons having energies above the threshold for the .sup.40 Ar(p,3n).sup.38 K reaction. The resulting potassium-38 is dissolved in a sterile water and any contaminating chlorine-38 is removed.

Abstract: Radioactive iodine, present as alkali metal iodides or iodates in an aqueous solution, is incorporated into an inert solid material for long-term storage by adding to the solution a stoichiometric amount with respect to the formation of a sodalite (3M.sub.2 O.3Al.sub.2 O.sub.3. 6SiO.sub.2.2MX, where M=alkali metal; X=I.sup.- or IO.sub.3.sup.-) of an alkali metal, alumina and silica, stirring the solution to form a homogeneous mixture, drying the mixture to form a powder, compacting and sintering the compacted powder at 1073 to 1373 K (800.degree. to 1100.degree. C.) for a time sufficient to form sodalite.

Abstract: A process for exchanging isotopes of hydrogen, particularly tritium, between gaseous hydrogen and water is provided whereby gaseous hydrogen depeleted in tritium and liquid or gaseous water containing tritium are reacted in the presence of a metallic catalyst.

Abstract: Volatile, radioactive substances, obtained in the reprocessing of nuclear fuel and contained in the gas mixtures formed and in the liquid wastes are retained and separated in several stages. In the first stage the higher nitrogen oxides contained in the gas mixtures formed in the dissolution of the nuclear fuel with nitric acid and in the denitration of the uranium and plutonium nitrates are reduced to nitric oxide (NO) and iodine is absorbed. In the second stage, the gas mixture of the first stage is separated into a fraction containing the volatile, radioactive substances and nitric oxide and a fraction mainly consisting of nitrogen and xenon. Oxygen is added to the liquid, radioactive substances and enriched with volatile, radioactive substances. The enriched oxygen and the fraction of the second stage consisting of volatile, radioactive substances and nitric oxide are jointly subjected to a chemical treatment and the oxygen is reacted with the nitric oxide.

Abstract: Apparatus for upgrading and final enrichment of heavy water comprising means for contacting partially enriched heavy water feed in a catalyst column with hydrogen gas (essentially D.sub.2) originating in an electrolysis cell so as to enrich the feed water with deuterium extracted from the electrolytic hydrogen gas and means for passing the deuterium enriched water to the electrolysis cell.

Abstract: A method and apparatus for removing tritium from heavy water and light water comprising contacting tritiated feed water in a catalyst column in countercurrent flow with hydrogen gas originating from an electrolysis cell so as to enrich this feed water with tritium from the electrolytic hydrogen gas and passing the tritium enriched water to an electrolysis cell wherein the electrolytic hydrogen gas is generated and then fed upwards through the catalyst column. The tritium content of the hydrogen gas leaving the top of the enricher catalyst column is further reduced in a stripper column containing catalyst which transfers the tritium to a countercurrent flow of liquid water.

Abstract: Process for the extraction of fission products contained in irradiated nuclear fuel elements which have been subject to a temperature of at least 1200.degree. C. during their irradiation prior to dissolving the fuel by the wet process. After mechanically treating the elements in order to decan and/or cut them they are brought into contact with water in order to pass the fission products into aqueous solution. The treated elements are then separated from the thus obtained aqueous solution. At least one of the fission products is then recovered from the aqueous solution. The fission products are iodine, cesium, rubidium and tritium.

Abstract: A process for modifying various inorganic compounds defined by the formula:M(OH).sub.z (HQO.sub.4).sub.2 -z/2.xH.sub.2 Owherein M is a metal ion selected from Groups IVA and IVB of the Periodic Table of Elements, Q is an anion selected from Groups VA and VIB of the Periodic Table of Elements, z is any value from 0 to 2 and x is a number of from 0 to 8, by replacing a hydrogen in the inorganic compound with a metal cation. Suitable cations include those elements selected from Groups IA, IIA, IIIA, IVA, IB, IIB, IIIB including the lanthanide and activide series, IVB, VB, VIB, VIIB and VIII of the Periodic Table of Elements and ammonium. Thereafter, elevation of the temperature causes modification of the crystalline structure of the exchanged compound and provides various novel crystalline phases.

Abstract: An extraction method of a high purity tritium gas from tritium-containing heavy water is disclosed. Tritium-containing heavy water is led from a heavy water source into an exchange reaction column wherein the heavy water is brought into contact with a tritium-containing heavy hydrogen to thereby transfer tritium in the heavy hydrogen into the heavy water by way of the exchange reaction to obtain a tritium-enriched heavy water. The resulting tritium-enriched heavy water is then led to a heavy hydrogen gas generator such as an electrolytic cell to generate a tritium-enriched heavy hydrogen, a part of which is recycled to the exchange reaction column and the remaining part thereof is led into a hot-wire type thermal diffusion column, e.g. cascade to enrich tritium. The thus enriched tritium gas is withdrawn from the thermal diffusion column cascade.

Abstract: A process for producing carbon monoxide and synthetic coal by treating carbohydrates with acid in the absence of any appreciable gaseous oxygen.

Abstract: Gases are stored by combining with a bed of capturing solids at elevated temperatures and pressures. The solids are placed in canisters which are then placed in an autoclave. The gases to be stored are fed directly to the canister via a conduit passing through the autoclave wall.

Abstract: Method for conditioning metallic waste shells of zirconium or zirconium alloys obtained during processing of irradiated nuclear reactor fuel elements for noncontaminating final storage. The waste shells are subjected to a controlled oxidation at increased temperature to produce noncombustible, stable waste products which consist substantially of zirconium dioxide. The noncombustible, stable waste products so-produced are brought to final storage.

Abstract: The invention relates to a process for reducing the level of radioactivity of a stream of light hydrocarbons by passing the stream through sulfided solid particles.

Abstract: Radioactive ruthenium, molybdenum and technetium which are by-products of the fission of U.sup.235 are prevented from contaminating the environment during nuclear fuel reprocessing procedures by passing the radioactive ruthenium, molybdenum and/or technetium oxides over a trapping agent selected from the group consisting of alkaline earth compounds, lanthanide compounds and lead compounds at a temperature of over 500.degree. C. leading to the formation of nonvolatile ruthenates, molybdates and technetates. By this process volatile radioactive RuO.sub.4, MoO.sub.3 and Tc.sub.2 O.sub.7 are kept from escaping into the atmosphere during nuclear fuel reprocessing. The stable ruthenates, molybdates and technetates thus formed can then be easily isolated and contained during the period of maximum radioactive decay.

Abstract: A technetium-99m-stannous-phosphate complex in which the phosphate moiety includes pyrophosphate and in which no more than 5 to 15% or 20% by weight of such phosphate moiety is a linear polyphosphate of molecular weight greater than pyrophosphate, a method of making the same, a method of using the same by in vivo intravenous administration to a mammal of the sterile, nonpyrogenic complex followed by radioassay scanning or imaging the skeletal structure, and a kit made up of a stannous-phosphate complex in which the phosphate moiety is pyrophosphate and in which no more than 5 to 15% or 20% by weight of such phosphate moiety is a linear polyphosphate of molecular weight greater than pyrophosphate.

Abstract: A method of and apparatus for separating krypton from radioactive waste gases which become free during the chemical dissolution of burnt-off fuel particles and contain krypton and xenon. Simultaneously with the core fuel particles conveyed to the chemical dissolution, such quantity of chemically inactive carrier gas intermixable with the waste gases is added to the substances bringing about the chemical dissolution that after purification of the waste gas mixture from gas components such as oxygen, carbon dioxide, nitrous oxide, hydrocarbons and water steam and after subsequent cooling of the waste gas mixture to the boiling temperature of the liquid nitrogen, the quantity of xenon contained in the waste gas mixture is quantitatively precipitated in solid form. Thereupon the waste gas mixture is cooled by means of liquid nitrogen, while simultaneously increasing the pressure, to such an extent that krypton is precipitated.

Abstract: An extraction apparatus for removing polonium-210 from irradiated bismuth by a pyrochemical extraction process comprises a melting chamber suitable for melting irradiated bismuth, a reservoir for melted bismuth, an extraction chamber suitable for holding molten caustic and having means for circulating molten bismuth from the reservoir through the extraction chamber whereby said bismuth can be repeatedly cycled in counter flow through the molten caustic and the polonium-210 is removed from the irradiated bismuth.

Abstract: A novel process and an apparatus are herein disclosed for separating molybdenum-99 from irradiated uranium.

Abstract: A technetium-99m-stannous-phosphate complex in which the phosphate moiety includes pyrophosphate and in which no more than 5 to 15% or 20% by weight of such phosphate moiety is a linear polyphosphate of molecular weight greater than pyrophosphate, a method of making the same, a method of using the same by in vivo intravenous administration to a mammal of the sterile, nonpyrogenic complex followed by radioassay scanning or imaging the skeletal structure, and a kit made up of a stannous-phosphate complex in which the phosphate moiety is pyrophosphate and in which no more than 5 to 15% or 20% by weight of such phosphate moiety is a linear polyphosphate of molecular weight greater than pyrophosphate.

Abstract: Uniform microspheres substantially or completely free from internal cavities and voids are prepared by spraying an aqueous hydrated metal oxide solution onto the surface of a water-immiscible organic liquid containing from 0.04 to 2.0 percent by volume of a surface active agent, the viscosities of each of the organic and inorganic phases plus the amount of surface active agent within the above range being selected such that there is sufficient surface active agent present to prevent the globules from adhering to each other yet an insufficient amount to prevent deformation from the substantially spherical shape.

Abstract: .sup.203 Pb-tris complex injected for use in the detection and localization of tumors. The lead-203 is produced from the deuteron bombardment of a thallium target and chemically separated from the thallium. The tris is added which complexes with the lead-203.

Abstract: A metallic foil coated with scandium tritide is treated so as to manifest a legally acceptable tritium emanation rate at temperatures above 225.degree. C, thereby becoming usable as a beta particle emitter is ionization detectors such as electron capture detectors or the like operated at high temperatures. The treatment includes heating the foil for a length of time sufficient to cause the foil's tritium emanation ratio to reach a value which corresponds to a legally acceptable emanation ratio for the foil at selected operating temperatures above 225.degree. C.

Abstract: This invention relates to novel carbonyl mixed metal salts, containing more than one metal and having the formula:M [T.sub.y T'.sub.12.sub.-y (CO).sub.30 ]wherein M is a divalent metal cation which is one of beryllium, magnesium, calcium, strontium, radium, manganese, iron, ruthenium, cobalt, nickel, palladium, platinum, zinc, cadmium, mercury, cerium and europium, T and T' are each different metals selected from the group consisting of cobalt, iridium and rhodium, and y may be any whole number between 1 and 11.These compounds are useful catalysts in the reaction between carbon monoxide and hydrogen to produce oxygenated compounds such as methanol, ethylene glycol, glycerine and 1,2-propylene glycol.

Abstract: Apparatus and method for providing larger quantities of higher purity polonium suitable, as vapor distilled, for heat source elements for radioisotopic generators or the like.

Abstract: This invention relates to novel carbonyl mixed metal salts, containing more than one metal and having the formula:M.sub.2 T.sub.y T'.sub.12.sub.-y (CO).sub.30wherein M is a monovalent metal cation which is one of lithium, sodium, potassium, rubidium, cesium, francium, rhodium, copper, silver, gold, iridium, indium, and thallium, T and T' are each different metals and each is one of cobalt, rhodium and iridium and y may have values from 1 to 11.These compounds are useful catalysts in the reaction between carbon monoxide and hydrogen to produce oxygenated compounds such as methanol, ethylene glycol, glycerine and 1,2-propylene glycol.

Abstract: Bombarding a cesium heat pipe with high energy particles causes a spallation reaction which produces vapors of .sup.123 Xe and contaminants. The contaminants are removed in a dry ice cold trap while the .sup.123 Xe condenses in a liquid nitrogen trap where it decays to .sup.123 I.

Abstract: Spallation reactions are induced in Mo targets with 200-800 MeV protons to produce microcurie to millicurie amounts of a variety of radionuclides. A six-step radiochemical procedure, incorporating precipitation, solvent extractions, and ion exchange techniques, has been developed for the separation and purification of Sr radioactivities from other spallation products and the bulk target material. Radiostrontium can be quantitatively recovered in a sufficiently decontaminated state for use in biomedical generator development.

Abstract: After a first extraction of an aqueous nitric acid solution of spent nuclear fuel by a suitable organic solvent and a first washing of the resulting organic phase by an aqueous solution to remove tritiated water, the organic phase is submitted to a second washing with a volume of dilute aqueous solution of nitric acid free from tritium, said volume being substantially smaller than that of the organic phase, whereby the organic phase is rendered substantially tritium-free and contamination by tritium in the following stages of the process is avoided.

Abstract: An improved .sup.82 Sr-.sup.82 Rb radioisotope generator system, based upon the complexing ion exchange resin Chelex-100, has been developed. Columns of this material can be easily and rapidly milked, and the Rb-Sr separation factor for a fresh generator was found to be > 10.sup.7. Approximately 80 percent of the .sup.82 Rb present was delivered in a 15-ml volume of aqueous 0.2 M NH.sub.4 Cl solution. After more than 6 liters of eluant had been put through the generator, the Rb-Sr separation factor was still observed to be > 10.sup.5, and no unusual strontium breakthrough behavior was seen in the system over nearly three .sup.82 Sr half lives.

Abstract: The time taken to reduce concentration of radioactive gas in the coolant of a nuclear reactor to permissible levels during refueling or the like is reduced by injecting into the reactor coolant a quantity large compared to the quantity of fission gas, of stable gas of the same atomic number as each radioactive gas. The fission gas includes both stable and radioactive isotopes, the quantity of stable isotopes being large compared to the quantity of radioactive isotopes. The stable gas added and the fission gas of each atomic number are dissolved as one gas in the reactor fluid and are purged together, the added stable gas accelerating the dissolution of the radioactive gas.

Abstract: A process for the removal of radon from hydrocarbon streams by insertion and removal of radon-selective carriers.