Abstract: An embodiment of the present disclosure is directed to a brachytherapy source assembly including a guiding wire and a brachytherapy capsule located at a distal end of the guiding wire. The capsule includes a chamber defined by a wall for holding a radioactive source. At least a portion of an exterior surface of the wall of the capsule includes at least one of a friction-reducing coating, a wear-resistant coating, and a wear-indication coating a coating.

Abstract: A method for selectively extracting sedimentogenic strontium and barium from terrigenous elastic sediments to reflect the difference between marine and continental sedimentary environments is disclosed. The method comprises collecting loose sediment, removing visible biogenic clasts, baking the sample and crushing the sample to a grain size no larger than 100-mesh. The method further comprises weighing the sample, reacting the sample in acetic acid or acetic acid-acetate solution, stirring or oscillating the sample at room temperature and normal pressure, separating the solid and liquid after reaction and analyzing strontium and barium in the supernatant. The gained Sr/Ba ratio of the supernatant reflects whether the sediments were deposited in a marine or a continental sedimentary environment.

Abstract: Compositions comprising nanosized objects (i.e., nanoparticles) in which at least one observable marker, such as a radioisotope or fluorophore, is incorporated within the nanosized object. The nanosized objects include, for example, metal or semi-metal oxide (e.g., silica), quantum dot, noble metal, magnetic metal oxide, organic polymer, metal salt, and core-shell nanoparticles, wherein the label is incorporated within the nanoparticle or selectively in a metal oxide shell of a core-shell nanoparticle. Methods of preparing the volume-labeled nanoparticles are also described.

Abstract: A glass radiation-source with customized geometries to maximize receipt of radiation into treatment areas that is formed from either neutron-activated glass, radioisotopes molecularly bonded to glass, or radioisotopes encased within glass.

Abstract: A gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more nonmetals which upon irradiation do not produce products capable of sustained emission of radiation which would unacceptably interfere with the gamma radiation of 75Selenium. A further gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more metals or nonmetals, the neutron irradiation of which does produce products capable of sustained emission of radiation which would acceptably complement the gamma radiation of 75Selenium. Further, the gamma radiation source may have components that are separately irradiated before being combined and the components may be of natural isotopic composition or of isotopically modified composition so that the subsequent radiation peaks may also be adjusted in relative frequency.

Abstract: Neutron source comprising a composite, said composite comprising crystals comprising BeO and AmBe13, and an excess of beryllium, wherein the crystals have an average size of less than 2 microns; the size distribution of the crystals is less than 2 microns; and the beryllium is present in a 7-fold to a 75-fold excess by weight of the amount of AmBe13; and methods of making thereof.

Abstract: The present invention provides a composition used for increasing calmodulin and a method thereof. A far-infrared ray is released by a far-infrared releasing substance in the composition so as to induce intracellular calmodulin concentration increased in organisms. The far-infrared releasing substance consists of ceramic minerals and mainly comprises 80-99.9 wt % of oxide minerals including 60-95 wt % of the mineral alumina. The far-infrared releasing substance according to the present invention has the advantages of easy to carry and continuously working, so as to significantly improve the shortcoming of drugs with short-term acting.

Abstract: The present invention relates generally to synthesis of radioactive material, such as a tritiated polymer, and an apparatus for generating electrical current from the nuclear decay process of a radioactive material. In one embodiment, the invention relates to an energy cell (e.g., a battery) for generating electrical current derived from particle emissions occurring within a radioactive material such as a tritiated polymer) on pore walls of a porous semiconductor. The radioactive material may be introduced into the energy cell by a wetting process.

Abstract: The present invention deals with the encapsulation of a nuclear source of energy (Strontium 90) in order to generate up to 600 degree Celsius. The encapsulated Strontium 90 is destined to be used to generate steam, or to liquefy the viscous oil of wells, as well as the paraffin, covering the cables used in the extraction of oil, which makes the extraction difficult or impossible. The encapsulated Strontium 90 has to be transported into a metal housing already patented by Ioan G. Crihan, one of the undersigned authors (FIG. 1).

Abstract: Composite scintillator material consisting of a binderless sintered mixture of a Lithium (Li) compound containing 6Li as the neutron converter and Y2SiO5:Ce as the scintillation phosphor, and the use of this material as a method for neutron detection. Other embodiments of the invention include various other Li compounds.

Abstract: An adhesive containing a far infrared radiation ceramic powder emitting far infrared rays and a radiation source ceramic powder emitting radiations and anions. The radiation source ceramic powder includes silicon dioxide, aluminum oxide, iron oxide, titanium oxide, calcium oxide, magnesium oxide, potassium oxide, sodium oxide and zirconium and/or radium. The adhesive according to the present invention relaxes human beings, helps spontaneous recovery from diseases and improves health by the synergistic effects of far infrared rays, anions and radiations.

Abstract: A gamma radiation source comprising selenium-75 or a precursor therefore, wherein the selenium is provided in the form of one or more thermally stable compounds, alloys, or mixed metal phases.

Abstract: The present invention relates to the use of nanoscintillation systems, or nanoparticles containing fluor molecules, that can be used to detect an electron-emitting or alpha-particle-emitting radioisotope in the absence of organic-solvents commonly used in organic-based liquid scintillation cocktails. The invention also relates to compositions and use of three oil-in-water microemulsion precursors that can be engineered rapidly, reproducibly, and cost-effectively to produce useful nanoparticles less than 100 nanometers.

Abstract: Preventing incomplete combustion of fuel in a heat apparatus and equipment.

Abstract: The present invention relates to the use of nanoscintillation systems, or nanoparticles containing fluor molecules, that can be used to detect an electron-emitting or alpha-particle-emitting radioisotope in the absence of organic-solvents commonly used in organic-based liquid scintillation cocktails. The invention also relates to compositions and use of three oil-in-water microemulsion precursors that can be engineered rapidly, reproducibly, and cost-effectively to produce useful nanoparticles less than 100 nanometers.

Abstract: An adhesive containing a far infrared radiation ceramic powder emitting far infrared rays and a radiation source ceramic powder emitting radiations and anions. The radiation source ceramic powder comprises silicon dioxide, aluminum oxide, iron oxide, titanium oxide, calcium oxide, magnesium oxide, potassium oxide, sodium oxide and zirconium and/or radium. The adhesive according to the present invention relaxes human beings, helps spontaneous recovery from diseases and improves health by the synergistic effects of far infrared rays, anions and radiations.

Abstract: A radiation source assembly and a connector press used in producing such assemblies. In the radiation source assembly, each of the cap connector and the female connector is provided with internal round threads on its pigtail fitting hole, thus engaging with the large-diameter coil of the pigtail at the internal round threads through a thread engagement prior to a compression process of the press. The assembly also allows a person to know whether both ends of the pigtail fully reach desired points within the two connectors, thus securing a precise compressing target portion during a compression process of the press. The inserted lengths of the pigtail relative to the two connectors are maximize accomplishing a desired linearity of the assembly. In the assembly, a target biasing spring is provided on the capsule lid and allows the disc targets within the source capsule to effectively maintain a desired condition as point sources regardless of the number of targets.

Abstract: Disclosed is a is an improved flood source, and method of making the same, which emits an evenly distributed flow of energy from a gamma emitting radionuclide dispersed throughout the volume of the flood source. The flood source is formed by filling a bottom pan with a mix of epoxy resin with cobalt-57, preferably at 10 to 20 millicuries and then adding a hardener. The pan is secured to a flat, level surface to prevent the pan from warping and to act as a heat sink for removal of heat from the pan during the curing of the resin-hardener mixture.

Abstract: A radiotheraputical source of Rhenium188 comprises metallic Tungsten188 or a metal oxide of Tungsten188. Therapeutic device using Rhenium188 comprise a radioactive source for the in situ generation of Rhenium188 from Tungsten188.

Abstract: A nonradioactive glass in particulate form adapted for radiation therapy in a mammal comprise a biodegradable rare earth-lithium borate glass material of a specified composition which, upon being subjected to an effective amount of neutron irradiation, will produce a beta or gamma emitting radioisotope, the radioisotope being distributed throughout the glass material, the glass upon being introduced into a body fluid for radiation therapy being adapted to react therewith causing the radioisotope to form an insoluble compound on the surface of the glass material which is retained in the glass material and thereby prevented from escaping from the treatment site. Radioactive glasses and methods for carrying out radiation therapy with such radioactive glasses are also disclosed.

Abstract: The transition metal-catalyzed amination of aryl halides, in conjunction with an orthogonal protective group scheme, forms the basis of two routes to oligoaniline precursors. The oligoaniline precursors are soluble in a variety of common organic solvents, and are easily converted to the deprotected oligoanilines. The method allows the preparation of oligoanilines of even or odd chain lengths, and the incorporation of a variety of functional groups into the oligomers. Polyanilines of low polydispersity can also be prepared by this method.

Abstract: A nonradioactive glass in particulate form adapted for radiation therapy in a mammal comprise a biodegradable rare earth-lithium borate glass material of a specified composition which, upon being subjected to an effective amount of neutron irradiation, will produce a beta or gamma emitting radioisotope, the radioisotope being distributed throughout the glass material, the glass upon being introduced into a body fluid for radiation therapy being adapted to react therewith causing the radioisotope to form an insoluble compound on the surface of the glass material which is retained in the glass material and thereby prevented from escaping from the treatment site. Radioactive glasses and methods for carrying out radiation therapy with such radioactive glasses are also disclosed.

Abstract: Radiopharmaceutical formulations for complexes comprising at least one radionuclide complexed with a ligand, or its physiologically-acceptable salts thereof, especially .sup.153 samarium-ethylenediaminetetramethylenephosphonic acid, which optionally contains a divalent metal ion, e.g. calcium, and is frozen, thawed, and then administered by injection.

Abstract: Additives are proposed for compositions comprising radiolabelled organic compounds e.g. 32P-labelled nucleotides. Stabilisers are selected from tryptophan, para-aminobenzoate, indoleacetate and the azole group. Dyes are selected from Sulphorhodamine B, Xylene Cyanol, Azocarmine B and New Coccine. Preferred compositions contain both stabiliser and dye.

Abstract: A stabilized radionuclide-colloid composition useful in therapeutic radiation ablation therapies is disclosed. The composition contains a viscosity modifier layered mixed metal hydroxide and optionally an ion exchange medium to stabilize the radioactive colloid.

Abstract: A method of preparing a stable, therapeutic radiopharmaceutical composition comprised of an alpha- or beta-emitting radionuclide and a ligand by lyophilizing a solution of the complex. The radionuclide preferably has a half-life of at least twelve hours. The invention also is directed to stable lyophilized radiopharmaceutical compositions prepared by this method. The invention is particularly suited to the preparation of radionuclide-labeled antibodies in a stable form which merely requires reconstitution at the point of use.

Abstract: The invention relates to a method of localizing and quantifying regional energy metabolism, in particular regional ischemia, in a warm-blooded living being, comprising administering to said being a diagonstically effective quantity of a radiolabelled L-homocysteine or a radiolabelled functional derivative thereof. The invention further relates to a pharmaceutical composition to be used for performing the above method.

Abstract: A high melting metal silicide sputtering target which comprises a fine texture whose stoichiometric composition grains of MSi.sub.2, where M represents a high melting metal, have a maximum grain size of 20 .mu.m, whose free silicon grains have a maximum grain size of 50 .mu.m and whose oxygen content is not more than 200 ppm and has a density ratio to the theoretical density of 99% or more has good film characteristics including the reduction in the number of grains formed on the sputtered film and is useful as an electrode material or a wiring material in semi-conductor devices.

Abstract: A cathode is made from tungsten powder using as an impregnant the product rmed from adding about 1 mole of a member selected from the group consisting of zirconium, zirconium dioxide, hafnium, hafnium dioxide, uranium, uranium dioxide, titanium, and titanium dioxide to about 50 to about 100 moles of a compound selected from the group consisting of Ba.sub.3 Al.sub.2 O.sub.6, Ba.sub.3 WO.sub.6, and Ba.sub.4 Al.sub.2 O.sub.7.

Abstract: A method is disclosed for separating and immobilizing a radioactive material comprising: contacting an aqueous medium containing said radioactive material with a reactive composition comprising at least one alkali metal, at least one Group IIIB metal and at least one phosphorus oxide; maintaining said reactive composition in contact with said aqueous medium for an effective period of time to react a desired amount of said radioactive material with said reactive composition to form a radioactive-material-containing composition; and separating said radioactive-material-containing composition from said aqueous medium. Radioactive-material-containing compositions exhibiting low leach rates are also disclosed.

Abstract: A capsule for encapsulating radioactive material for radiation treatment comprising two or more interfitting sleeves, wherein each sleeve comprises a closed bottom portion having a circumferential wall extending therefrom, and an open end located opposite the bottom portion. The sleeves are constructed to fit over one another to thereby establish an effectively sealed capsule structure.

Abstract: A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium.

Abstract: Radioactive microspheres for radiation synovectomy of arithmetic joints in a mammal comprise a biodegradable glass material and a beta radiation emitting radioisotope chemically dissolved in and distributed substantially uniformly throughout the glass material. The biodegradable glass material may be lithium silicate, lithium aluminosilicate, lithium aluminoborate, lithium germanate, lithium aluminogermanate, potassium silicate, potassium aluminosilicate, potassium, aluminoborate, potassium germanate or potassium aluminogermanate and the beta radiation emitting radioisotope may be samarium-153, holmium-166, erbium-169, dysprosium-165, rhenium-186, rhenium-188 or yttrium-90. Methods for preparing such microspheres and for carrying out radiation synovectomy of arthritic joints utilizing such microspheres are also disclosed.

Abstract: A drivable radioactive source capsule is provided which comprises a tubular body containing therein a plurality of radioactive sources. The said tubular body has a first end and a second end which is a terminus of the tubular body. A plug has an elongated closure portion with the diameter of the closure portion being substantially equal to the inside diameter of said tubular body. The closure portion is disposed within the tubular body through the second end thereof and is attached to the second end of the tubular body. The plug has a connection portion adjacent the closure portion with the diameter of the connecting portion being substantially equal to the outside diameter of the tubular body. An elongated flexible drive cable is connected to the connection portion of the plug.

Abstract: A partitioning radioactive tracer material is prepared by reacting an alkali-metal salt of radioactive iodine with chloroethanol in the presence of activated carbon.

Abstract: Apparatus is disclosed for the dry storage of heat-emitting radioactive waste materials. The latter are stored in tubes placed within a room having at least one cold air inlet and a hot air outlet. The distance between adjacent tubes and the distance between a tube and a wall of the room is such that a conically-shaped hot air boundary layer formed by natural convection around a tube is in contact neither with the boundary layer of another tube, nor with the wall of the room.

Abstract: A method for preparing radiopharmaceutical complexes that are substantially free of the reaction materials used to produce the radiopharmaceutical complex is disclosed. The method involves admixing in a suitable first solvent in a container a target seeking ligand or salt or metal adduct thereof, a radionuclide label, and a reducing agent for said radionuclide, thereby forming said radiopharmaceutical complex; coating the interior walls of the container with said pharmaceutical complex; discarding the solvent containing by-products and unreacted starting reaction materials; and removing the radiopharmaceutical complex from said walls by dissolving it in a second solvent, thereby obtaining said radiopharmaceutical complex substantially free of by-products and unreacted starting materials.

Abstract: A radiography source, preferably a cobalt-60 source constructed of a plurality of radioactive cobalt-60 pellets contained in an open capsule preferably constructed of titanium. The pellets are disposed in the capsule and compacted therein to reduce the source focal size. A plug is disposed in the open capsule and welded therewith. The cobalt and titanium materials are sufficiently different in atomic number to permit good X-ray analysis resolution.

Abstract: A radioactive microsphere for radiation therapy of a mammal comprising a biologically compatible glass material containing a beta or gamma emitting radioisotope distributed substantially uniformly throughout the glass. Advantageously, the radioisotope is produced by irradiation of the microsphere.

Abstract: Beryllium-7 labeled carbon particles made from the proton irradiation of carbon materials, preferably from dry carbon black are disclosed. Such particles are useful as gamma emitting radiotracers.

Abstract: Method of producing liquid equivalent solid gamma ray calibration standards comprising the steps of adding a first organic solvent to a calibrated aqueous solution of radioactive material, either in the form of a single isotope or mixed isotopes, to form a first solution; mixing the first solution with a polymerizible resin dissolved in a second organic solvent together with a hardening catalyst to form a second solution; and curing the second solution. With isotope standards requiring highly acidic conditions, a stabilizing agent is added to the first solvent to complex with metal and hydrogen ions so as to prevent plate-out.

Abstract: A stabilized composition comprising a solution of a radiolabeled compound and a diethylenetriamine is described. Preferred diethylenetriamines include, N,N-bis(2-aminoethyl) dithiocarbamic acid, di(2-dithiocarbamyl-ethyl) amine, and salts thereof.

Abstract: A radioactive .sup.57 Co source consists of the intermetallic composition CoSb.sub.3 which emits an energetically non-disintegrated 14.4 KeV line. This composition is strictly stoichiometrical and may be dissolved in excess Sb. The atom percent proportion of .sup.57 Co may be up to 25%.

Abstract: This invention relates to radioactive materials which are fixed, stored, entrapped, encapsulated, or otherwise rendered immobile in a glass matrix for extremely long periods of time. Radioactive material such as radioactive wastes are incorporated into a glass matrix by a process of "molecular stuffing" a porous glass either with a radioactive gas which is tapered in the porous glass by dissolution during sintering of the pores of the glass, or with a salt solution containing radioactive material such as CsNO.sub.3, Sr(NO.sub.3), etc., or with a combination of both salt solution and radioactive gas, followed by drying and sintering of the pores of the glass whereby these radioactive materials upon chemical change to their oxides, excepting of course the noble gases which remain in molecular form, become a part of the integrated glass structure.