Abstract: A generator system to provide iridium-191m for clinical imaging applications comprises an activated carbon adsorbent loaded with a compound containing the parent nuclide, osmium-191. The generator, which has a shelf-life in excess of two weeks and does not require a scavenger column, can be eluted with physiologically compatible saline.

Abstract: Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO.sub.2+x) and plutonium dioxide (PuO.sub.2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then is milled and subsequently granulated, pressed and sintered. The milling aid is expelled by subsequent drying processes or heat treatments (sintering). The milling process is controlled to obtain a primary grain size of less than two micrometers.

Abstract: Novel toxic compounds being useful as chemical warfare agents in various itions.The compound having the following structure: ##STR1## where n is an integer from 6 to 16 and where X is halide, sulfate, nitrate, hydrogenoxalate or perchlorate forming a stable salt.

Abstract: A process for producing a natural antioxidant from tea leaves comprising treating said tea leaves with a solvent selected from the group consisting of hot water (preferably 80.degree. C.-100.degree. C.), a 40-75% aqueous solution of methanol, a 40-75% aqueous solution of ethanol and a 30-80% aqueous solution of acetone to obtain an extract-containing solution; washing the extract-containing solution with chloroform to obtain a washed extract; combining the washed extract with an organic solvent to transfer said washed extract into said organic solvent; removing the organic solvent; and drying the resulting extract. The invention also provides the natural antioxidant produced by the aforesaid process.

Abstract: A solid fuel for generating H.sub.2 or D.sub.2 gases, comprising magnesium orohydride diammoniate (MBDA) or its deuterated analog as the H.sub.2 or D.sub.2 source, an oxidizer selected from LiNO.sub.3 and KNO.sub.3, and a binder of polytetrafluoroethylene is a thermally stable gas generator composition which yields greater than 12.5 weight percent H.sub.2 or D.sub.2. The MBDA weight percentages by weight ranges from 80-90, the oxidizer ranges from 5-15, and the binder ranges from 2-15.

Abstract: The invention relates to molded getter bodies for use in encapsulated electrical components. The getter bodies are formable into compressed body shapes in a simplified manner from a mixture of (A) a getter material consisting of activated carbon, zeolite, zirconium and mixtures thereof, (B) polyamide, and (C) polyethylene wax. The molded getter bodies of the invention have improved accuracy as to size, increased getter capacity, and uniform getter activity relative to the prior art.

Abstract: This invention relates to bleaching compositions. More particularly, this invention relates to bleaching compositions that provide effective and efficient bleaching performance on textiles. Such bleaching performance is obtained over an extremely wide class of stains and wide range of temperatures of the bleaching solution of pH. The bleaching compositions within the invention contain a halogenated peroxybenzoic acid and a bleach activator that contains a carbonyl carbon atom that can potentially react with such peroxybenzoic acid to form a diacyl peroxide compound or essentially any peroxycarboxylic acid and a bleach activator that contains a carbonyl carbon atom that has an alkyl group containing from about 5 to about 17 carbon atoms and can potentially react with a peroxycarboxylic acid to form a diacyl peroxide compound. In a highly preferred embodiment the bleaching compositions within the invention are detergent compositions.

Abstract: The novel compound plutonium pentafluoride may be prepared by the photodissociation of gaseous plutonium hexafluoride. It is a white solid of low vapor pressure, which consists predominantly of a face-centered cubic structure with a.sub.o =4.2709.+-.0.0005 .ANG..

Abstract: Wastes, in the form of liquids, solids and slurries, are converted to a mixture of a gas and an inorganic ash by introducing the waste as a finely atomized spray into a zone heated by means of a hot gas. Contact of the spray particles with the hot gas results in drying the waste and calcining and combusting the dried waste. The process is particularly useful with wastes containing hazardous materials such as radioactive substances.

Abstract: An alpha alumina monohydrate, AlO(OH), powder is produced which is capable of readily dispersing in aqueous solutions to yield a shear-rate thinning mixture. The alpha alumina monohydrate is made by reacting an acid reactant and a base reactant, wherein at least one contains aluminum, in an aqueous medium in proportions to yield a solution having a pH of from about 7.5 to 10. Then the mixture is given the unique heat treatment at a temperature of from about 60.degree. to 100.degree. C. for a period of from about 2 to 7 hours. The excess water is removed from the product such as by filtration. The solid can be optionally washed to remove by-product salts. The solid product can be readily redispersed in water to yield a shear-rate thinning liquid without the aid of any further acid or base or the use of excessive high shear mixing. The solid product can be further dried to recover a solid product with greater than 10% AlO(OH) and even greater than 35% AlO(OH).

Abstract: A shipping and transport cask for spent nuclear fuel elements. The cask includes a cylindrical cask body having an outer shell and a concentric inner tube. Four quadrant baskets are mounted within the inner tube. Each quadrant basket includes radial and peripheral walls of high thermal conductivity material. A plurality of fuel element-receiving modules and an inner quadrant heat conducting member are mounted within the quadrant baskets. The peripheral walls of the quadrant baskets are held firmly against the inner wall of the body by shims inserted between the radial walls of adjacent quadrant baskets. During assembly, the quadrant baskets are initially forced outwardly against the inner wall by means of expandable spreaders. The cask also includes removable trunnions and primary and secondary external fluid chambers filled with a neutron-attenuating fluid.

Abstract: A process is described for the solidification of concentrated boric acid waste solutions. The waste solution must have a boric acid concentration greater than 30% by weight. Sodium metasilicate is added to the boric acid waste solution and is mixed; a dry, hard product is formed. The process is not hindered by the presence of up to 40% dewatered bead resins.

Abstract: A method and apparatus for providing radionuclides of bismuth-212 and lead-212. Thorium-228 and carrier solution starting material is input to a radiologically contained portion of an isotopic generator system, and radium-224 is separated from thorium-228 which is retained by a strongly basic anion exchange column. The separated radium-224 is transferred to an accessible, strongly acidic cationic exchange column. The cationic column retains the radium-224, and natural radioactive decay generates bismuth-212 and lead-212. The cationic exchange column can also be separated from the contained portion of the system and utilized without the extraordinary safety measures necessary in the contained portion. Furthermore, the cationic exchange column provides over a relatively long time period the short lived lead-212 and bismuth-212 radionuclides which are useful for a variety of medical therapies.

Abstract: A process for separating isotopes by selective excitation of isotopic species of a volatile compound by tuned laser light. A highly cooled gas of the volatile compound is produced in which the isotopic shift is sharpened and defined. Before substantial condensation occurs, the cooled gas is irradiated with laser light precisely tuned to a desired wavelength to selectively excite a particular isotopic species in the cooled gas. The laser light may impart sufficient energy to the excited species to cause it to undergo photochemical reaction or even to photoionize. Alternatively, a two-photon irradiation may be applied to the cooled gas to induce photochemical reaction or photoionization. The process is particularly applicable to the separation of isotopes of uranium and plutonium.

Abstract: A composition comprising a support such as a porous silicate glass or silica gel or charcoal having interconnected pores and containing heavy metal cations of mercury, thallium, silver, platinum, palladium, lead or copper capable of forming a stable complex with an anion bonded to the support. The preferred heavy metal cation is a mercury cation. The composition is especially useful for removing radioactive iodine from liquid and gaseous waste streams.

Abstract: A process for removing metal species from solution comprising passing the liquid over a composition comprising a support such as a porous silicate glass or silica gel or charcoal having interconnected pores and containing water soluble amine complexing agents absorbed on the support capable of forming a stable complex with the metal species. The preferred amine complexing agent is triethylenetetramine. The process is especially useful for removing radioactive cobalt from liquid waste streams.

Abstract: A process and apparatus are described for separating heavy isotopes of hydrogen. The process uses multiple protium-deuterium, protium-tritium or deuterium-tritium exchange reactions between a metal protide and gaseous hydrogen alternately depleted and enriched in at least one heavy isotope of hydrogen. The apparatus for performing the process comprises two multistage reaction zones, one for forming a metal hydride enriched in at least one heavy isotope and one for converting the enriched hydride to a depleted hydride and enriched hydrogen gas. The apparatus is simple in design and the process is much less energy intensive than existing prior art processes.

Abstract: Multiple photon absorption from an intense beam of infrared laser light may be used to induce selective chemical reactions in molecular species which result in isotope separation or enrichment. The molecular species must have a sufficient density of vibrational states in its vibrational manifold that, is the presence of sufficiently intense infrared laser light tuned to selectively excite only those molecules containing a particular isotope, multiple photon absorption can occur. By this technique, for example, intense CO.sub.2 laser light may be used to highly enrich .sup.34 S in natural SF.sub.6 and .sup.11 B in natural BCl.sub.3.

Abstract: Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.

Abstract: A process for the recovery of the uranium present in phosphoric acid produced by a wet process in (A) by means of a suitable solvent (L.sub.9), which is carried out after separation of the gypsum in (B) formed in the attack operation, and elimination of the solid materials which are still in suspension, characterized in that, in order to avoid the formation of dross in the course of the operation of extracting the uranium which is previously reduced in (D), the step of eliminating the solid materials which are still in suspension is effected by a final solid-liquid separation operation in (C) and/or in (E), prior to extraction of the uranium in (F), in the presence of an added fraction of gypsum (S.sub.22) and/or (S.sub.23) resulting from the production of H.sub.3 PO.sub.4.