Abstract:
A process and apparatus for separating an isotope of an element from other isotopes of the element in a compound, where the compound is deposited as a monolayer on small glass beads, and the coated beads entrained in a carrier gas containing a scavenger gas. The entrained, coated beads are exposed to light from a laser that excites the one isotopic compound and causes reaction thereof with the scavenger gas, to form a reaction product, while the other isotopic compounds remain stable. The other isotopic compounds are then separated from the reaction product and the reaction product removed from the beads to provide the desired isotope.
Abstract:
The isotopes of zirconium can be partially or completely separated by loading an aqueous solution of an ionic compound of zirconium onto a cationic exchange resin which serves as the stationary phase of a chromatograph, eluting the compound with an aqueous acid and collecting distinct elution volumes representative of each isotope. In a preferred embodiment, the eluant is a strong mineral acid, such as hydrochloric acid and the chromatograph is of a type, such as a continuous annular chromatograph that it can be operated in a continuous, steady state manner.
Abstract:
The thermal neutron capture cross-section of zirconium may be altered by altering its natural isotope distribution through a steady state chromatographic separation of these isotopes using an anion exchange resin as the stationary phase of the chromatographic column. Zirconium is dissolved in a very strong acid which causes the formation of a zirconium anion, such as the ZrOCl.sub.4.sup.-2 anion formed in six normal hydrochloric acid, and eluted off the column with a weaker acid. Distinct elution volumes representative of each isotope are collected. In a preferred embodiment, the process also separates the zirconium from hafnium and the other impurities normally present in the product obtained by chlorinating zircon sand and utilizes a continuous annular chromatograph.
Abstract:
Disclosed is an inorganic polymeric cationic ion exchange matrix which is the condensation polymerized reaction product of components including an alkyl compound of an element that has a valence of at least three, water, and a dopant having groups including an ion exchangeable moiety and a replaceable hydrogen. The ion exchange matrix is preferably made by adding the water to the alkyl compound first followed by the addition of the dopant, followed by heating to dryness. The resulting product is a powder or granule that can be used as an ion exchange matrix by placing it in a column and passing a solution through it which contains metal ions that are exchanged with ions on the polymer.
Abstract:
A fuel channel (5) for a fuel element (1) to a fission reactor, where the fuel element comprises an inlet (9), an outlet (11) and a plurality of elongated fuel rods (3), which fuel rods each comprises a nuclear fuel and are adapted to transfer energy to a streaming medium during operation of the fission reactor. The fuel channel comprises a casing (7) adapted to surround the fuel rods between the inlet and the outlet. The casing is adapted during operation of the fission reactor to guide the streaming medium along the fuel rods from the inlet to the outlet and be subjected to irradiation from the fuel rods. The casing is manufactured from a ceramic material.
Abstract:
A method of recovering contaminating or valuable components from a solid feed material (10), includes feeding the material (10) into an optional grinder as a pretreatment (12), then into a heated melter (14) along with a material (16) that provides fluorine, to provide a molten or semi-molten material, where the molten material is then reacted with water or an acid solution (22) in vessel (20), to form a dissolved molten or semi-molten salt in solution, which can be passed to extractor (26) or the like and provide a concentrated stream of the valuable or contaminating components (30).
Abstract:
The removal of organics and volatile metals from soils using thermal desorption comprises moving contaminated materials, positioned on a belt conveyor, through a chamber (32) under oxygen conditions, temperature conditions, and residence time effective to substantially avoid incineration of the contaminants, while volatilizing the contaminants and producing a processed material that is substantially decontaminated, where the volatilized contaminants are carried from the chamber (32) by a transport gas which is passed through a packed tower (70) where quench/scrubbing liquid flows countercurrent to gas flow, for producing a substantially cleaned gas and a contaminated liquid concentrate. The gas may be passed through a further gas cleaning system (86) prior to discharge into the atmosphere, while the liquid concentrate is passed through a water treatment system (90) for producing substantially cleaned water which may be passed through an air cooler (92) and recycled back to cool the processed material. Steam from moist contaminated material can be used as a cocurrent transfer gas.
Abstract:
A nuclear reactor having a liquid metal or molten salt coolant in a riser space 130′, has a cylindrical containment vessel 134 with a reactor vessel 120′, at least two lobes 121, preferably three to nine lobes 121, each lobe 121 interconnected with the other lobe(s) and each containing a fast reactor core, 116′, 116″, 116″ and 116″″.
Abstract:
The present invention relates to nuclear fuel compositions including triuranium disilicide. The triuranium disilicide includes a uranium component which includes uranium-235. The uranium-235 is present in an amount such that it constitutes from about 0.7% to about 5% by weight based on the total weight of the uranium component of the triuranium disilicide. The nuclear fuel compositions of the present invention are particularly useful in light water reactors.
Abstract:
A multi-pressure hybrid sulfur process (2) contains at least one electrolyzer unit (16) which provides liquid H2SO4 to a preheater/vaporizer reactor (20) operating at a pressure of from 1 MPa to 9 MPa to form gaseous H2SO4 which is passed to a decomposition reactor (14) operating at a pressure of from 7 MPa to 9 MPa, where decomposed H2SO4 is passed to at least one scrubber unit (14) and at least one electrolyzer unit (16) both preferably operating at a pressure of 0.1 MPa to 7 MPa, where an associated Rankine Cycle power conversion unit (50) supplies electricity.
Abstract translation:多压混合硫工艺(2)包含至少一个电解槽单元(16),该电解器单元(16)向在1MPa至9MPa的压力下操作的预热器/蒸发器反应器(20)提供液体H 2 SO 4,以形成通过的气态H 2 SO 4 到分解反应器(14),其在7MPa至9MPa的压力下操作,其中分解的H 2 SO 4通过至少一个洗涤器单元(14)和至少一个电解器单元(16),优选在0.1的压力下操作 MPa至7MPa,其中相关的朗肯循环功率转换单元(50)供电。