36 results about "Americium" patented technology

A system and method for the extraction of americium from radioactive waste solutions. The method includes the transfer of highly oxidized americium from an acidic aqueous feed solution through an immobilized liquid membrane to an organic receiving solvent, for example tributyl phosphate. The immobilized liquid membrane includes porous support and separating layers loaded with tributyl phosphate. The extracted solution is subsequently stripped of americium and recycled at the immobilized liquid membrane as neat tributyl phosphate for the continuous extraction of americium. The sequestered americium can be used as a nuclear fuel, a nuclear fuel component or a radiation source, and the remaining constituent elements in the aqueous feed solution can be stored in glassified waste forms substantially free of americium.

A process which allows separation of americium present in an acid aqueous phase or in an organic phase from the other metal elements also found in this phase, by complexation of the americium with a water-soluble ethylenediamine derivative; and a process for selective recovery of americium from an acid aqueous phase containing, in addition to americium, other metal elements, which comprises the application of this separation process.

The invention relates to a nitride nuclear fuel characterized in that the nitride fuel is a pellet of a material with a single-phase solid solution of elements comprising at least a nitride of americium (Am), and that the material has a density of around 90% of the theoretical density. The invention further relates to a method for producing the said nuclear fuel by using the steps: mixing of starting powders, sintering of the powders into a dense pellet and a subsequent heat treatment.

The method shows how to violate predictions of quantum mechanics for matter. For light, the method has been disclosed in patent application Photon Violation Spectroscopy. The methods are different in specifying different methods for light and matter. For matter, the method typically uses the single 5.5 MeV alpha (He++) emitted from the radioisotope Americium-241 in spontaneous decay, a thin gold foil beam splitter, and two surface barrier alpha detectors. The detectors deliver a characteristic electrical pulse with amplitude proportional to matter wave energy. A circuit reads the coincidence rate and singles rates of pulses from the two detectors. Quantum mechanics predicts that the particle would go one way or the other at the beam splitter, and coincident detections of pulses characteristic of such a particle would occur only at an easily calculated chance rate. However, the method at hand shows such characteristic pulses occur in coincidence at a rate greatly exceeding chance. By exceeding chance the method demonstrates surpassing a binding energy threshold and predictions of quantum mechanics. The degree above chance is a new measure in fundamental physics and is usable as a material science probe of the beam splitter. An apparatus specially designed to test for the absence of true coincidences and then perform a beam splitting test to show split-beam coincidences becomes useful in applying the method of Particle Violation Spectroscopy to material science. Fundamental discoveries in physics have been made with this method; therefore it is a method of discovery in physics.

The invention discloses a determination method of plutonium age in a trace plutonium sample. The method comprises the following steps of: adding plutonium and the isotopic diluents of daughter americium thereof, namely, Pu and Am, in the sample; adding sodium nitrite for price adjustment; and then loading a TEVA resin column, using a chemical separation method to respectively obtain a Pu component and an Am component, and using a multi-receiving inductive coupling plasma mass spectrometry to measure the Pu component and the Am component respectively to obtain the values of Pu/Pu and Am/Am . According to the amount of the added diluents, the value of Pu/Am is calculated and substituted in the age-calculating formula to obtain the age of plutonium. The deviation between the age measured by the method and the reference value is within 5%.

The invention relates to the technical field of nuclear fuel aftertreatment and particularly discloses a device for measuring americium and cesium in aftertreatment feed liquid. A NaI detector is arranged in an area defined by central holes of a lead sheath A, a lead sheath B and a lead sheath D, and a connecting line of the NaI detector penetrates out of a slot in the lead sheath B to be connected with a multi-channel spectrometer; the multi-channel spectrometer is connected with a computer through a data line; and gamma ray signals are converted into electric signals by the NaI detector, theelectric signals are screened by the multi-channel spectrometer and then transmitted into the computer, and automatic sample measuring is realized. The device can effectively shield interference of environmental gamma rays in a measuring system, the multi-channel spectrometer is utilized, thus the gamma radioactivity concentrations of cesium-137 and americium-241 can be measured simultaneously, and the measuring result is directly read by software.

Disclosed is a full-wave band spectral scanner. The full-wave band spectral scanner mainly comprises a light source device, a photoseparation device, a primary reflecting device, a standard device, a secondary reflecting device, a dimming control device, a third reflecting device, a sample feeding device, a fourth reflecting device, a signal amplifying device, a signal correcting device, a signal analyzing device and a signal recording device. An outer cover of the light source device is made of hafnium and rutherfordium alloy. A ten-color glass filter disc is arranged in the light source device, the surface of the filter disc is covered with a meta-bromic acid pentaniobate composite filter film with the thickness being 20 microns, and a near ultraviolet optical filter and a far infrared optical filter are arranged in the light source device. A rhodium and osmium nitrate hexahydrate nano composite filter film is arranged in the near ultraviolet optical filter, a high energy light-emitting electrode is arranged in the light source device, and the electrode is made of americium and berkelium oxide alloy. An octahedral prism and a double-oblique crystal grating are arranged in the photoseparation device, and the octahedral prism and the double-oblique crystal grating are alternately arrayed in a series connection mode. A parabolic mirror, a hyperbolic mirror and an ellipsoidal lens are arranged in the primary reflecting device.

The invention discloses a nuclear reactor long-life neutron source device and a using method, the device comprises a neutron source assembly capable of installing a long-life neutron source in a sealing mode, and the neutron source assembly is connected with a reactor control rod driving mechanism. The neutron source assembly is inserted into or pulled out of a reactor core through the reactor control rod driving mechanism; the long-life neutron source can be an americium-beryllium source or a plutonium-beryllium source. According to the invention, the consumption of the neutron source material during the operation of the reactor can be obviously reduced, and the long-life characteristic of the neutron source material is maintained, so that the neutron source material can be repeatedly used in one or more units, and the uncertainty of the project cost and project progress of primary neutron source material purchase of each newly built nuclear power plant unit in China is avoided.

The proposed invention relates to processes of extraction and concentration of radio nuclides and can be used in radiochemical technologies when processing liquid radioactive wastes.

A method for extraction of americium from liquid radioactive wastes and its separation from rare-earth elements comprises simultaneous extraction of americium and rare-earth elements from radioactive nitrate solution with neutral solution of organic extracting agent in polar fluorinated organic solvent, washing of saturated with metals organic phase, selective re-extraction of americium. N,N,N′,N′-tetraalkyl-amide of diglycolic acid is used as an extracting agent and solution containing 5-20 g/L of complexon, 5-60 g/L of nitrogen-containing organic acid and 60-240 g/L of salting-out agent is used as a solution for re-extraction of americium.

Technical effect is the extraction of americium from acidic liquid radioactive solutions and its separation from all rare-earth elements in a single extraction cycle.

A high-sensitivity atomic spectral-line analysis instrument is characterized by mainly comprising a high-voltage discharging light-beam apparatus, a spectrum collection apparatus, a sample vaporization apparatus, a sample introduction apparatus, a light-beam filtering apparatus, a spectral-line separating apparatus, a spectrum development apparatus, a spectra-line conversion apparatus and a spectra-line display and recording apparatus; the high-voltage discharging light-beam apparatus comprises a high-voltage discharging light-beam electrode, and the electrode material is an americium einsteinium oxide alloy material; the spectrum collection apparatus comprises an nonagonal-pyramid-type focusing reflection lens, and the surface of the lens is plated with an ammonium magnesium octachromate-berkelium niobium bromide nanometer composite light-transmitting film with the thickness of 3.8 mu m; the sample vaporization apparatus comprises a high-temperature vaporization electrode, and the electrode material is a technetium oxide material; and the spectra-line separation apparatus comprises an nonagonal-prism type spectrum separation lens, the surface of the lens is plated with a spectra-line filtering membrane with the thickness of 10 mu m, and the filtering membrane is a neodymium ytterbium tetradecaphosphate composite membrane.

The invention discloses a destructible americium-beryllium neutron source and belongs to the technical field of nuclear application. According to the invention, a device structure is designed so thatwhen an americium-beryllium neutron source is needed to be destroyed, a source core of a radioactive source is soaked by a strong alkali solution, and metal beryllium in the source core is dissolved;then AmO2 in the source core is separated from the metal beryllium by using a filter screen, so that the alpha particles emitted from 241Am are prevented from bombarding the metal beryllium, a 9Be(alpha,n)12C reaction is stopped, and then the production of neutrons is stopped. According to the invention, a scrapped americium-beryllium neutron source can be conveniently destroyed, so that neutronsare no longer ejected, the harm to human bodies is reduced, and the treatment cost of the discarded americium-beryllium neutron source is reduced; meanwhile, the remaining AmO2 can be used as a low-energy gamma source, so that the repeated use of radioactive waste materials is realized.