A radionuclide separating system for separating a 213Bi daughter radionuclide from a 225Ac parent radionuclide, the radionuclide separating system comprising: an inlet for loading a liquid solution comprising the 225Ac parent radionuclide onto a column; the column comprising a sorbent material wherein the sorbent material is capable of interacting with the 225Ac parent radionuclide and 213Bi daughter radionuclide so as to allow selective desorption of the 225Ac parent radionuclide and/or the 213Bi daughter radionuclide at a different moment in time; and an outlet for selectively obtaining the 213Bi daughter radionuclide based on the selective desorption of the 225Ac parent radionuclide and the 213Bi daughter radionuclide, wherein the sorbent material is a carbon-based sorbent material.
C22B 3/24 - Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means by adsorption on solid substances, e.g. by extraction with solid resins
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
A liquid target system for the production of radio-isotopes, includes a boiling chamber for containing the liquid, being water or heavy water, and basic chemicals, being salts having a positive enthalpy for water, from which the radio-isotopes can be produced using irradiation, the boiling chamber comprising an irradiation window for allowing the liquid and basic chemicals to be irradiated, causing the liquid to evaporate into vapor, wherein the liquid target system is configured so that overheating of the liquid target is controlled by the thermodynamics of the evaporation process.
G21G 1/04 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators
3.
PURIFICATION OF TARGET MATERIAL FOR THE PRODUCTION OF RADIO-ISOTOPES
222O, the method comprises lowering the temperature of the solution to maximise the precipitation of the target material and reduce the solubility of the target material in the remaining liquid, separating the liquid containing the optionally present radio-isotopes from the precipitated target material, and preparing the precipitated target material for re-use in the production of radio-isotopes by re-irradiation for the production of radio-isotopes.
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
B01D 17/00 - Separation of liquids, not provided for elsewhere, e.g. by thermal diffusion
C22B 60/00 - Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
4.
PURIFICATION OF TARGET MATERIAL FOR THE PRODUCTION OF RADIO-ISOTOPES
B01D 17/00 - Separation of liquids, not provided for elsewhere, e.g. by thermal diffusion
C22B 60/00 - Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
A liquid target system (1) for the production of radio-isotopes, the liquid target system (1) comprising a boiling chamber (2) for containing the liquid, being water or 5heavy water, and basic chemicals, being salts having a positive enthalpy for water, from which the radio-isotopes can be produced using irradiation, the boiling chamber (2) comprising an irradiation window for allowing the liquid and basic chemicals to be irradiated, causing the liquid to evaporate into vapor, wherein the liquid target system is configured so that overheating of the liquid target (8) is controlled by the 10thermodynamics of the evaporation process.
G21G 1/04 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators
H05H 6/00 - Targets for producing nuclear reactions
A radionuclide separating system for separating a 213Bi daughter radionuclide from a 225Ac parent radionuclide, the radionuclide separating system comprising: an inlet for loading a liquid solution comprising the 225Acparent radionuclide onto a column (10); the column (10) comprising a sorbent material wherein the sorbent material is capable of interacting with the 225Acparent radionuclide and 213Bi daughter radionuclide so as to allow selective desorption of the 225Ac parent radionuclide and/or the 213Bi daughter radionuclide at a different moment in time; and an outlet for selectively obtaining said 213Bi daughter radionuclide based on said selective desorption of the 225Ac parent radionuclide and the 213Bi daughter radionuclide, wherein the sorbent material is a carbon-based sorbent material.
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
C22B 3/42 - Treatment or purification of solutions, e.g. obtained by leaching by ion-exchange extraction
A radionuclide separating system for separating a 213Bi daughter radionuclide from a 225Ac parent radionuclide, the radionuclide separating system comprising: an inlet for loading a liquid solution comprising the 225Acparent radionuclide onto a column (10); the column (10) comprising a sorbent material wherein the sorbent material is capable of interacting with the 225Acparent radionuclide and 213Bi daughter radionuclide so as to allow selective desorption of the 225Ac parent radionuclide and/or the 213Bi daughter radionuclide at a different moment in time; and an outlet for selectively obtaining said 213Bi daughter radionuclide based on said selective desorption of the 225Ac parent radionuclide and the 213Bi daughter radionuclide, wherein the sorbent material is a carbon-based sorbent material.
B01D 15/00 - Separating processes involving the treatment of liquids with solid sorbentsApparatus therefor
C22B 3/42 - Treatment or purification of solutions, e.g. obtained by leaching by ion-exchange extraction
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
8.
METHODS AND SYSTEMS FOR THE PRODUCTION OF ISOTOPES
A method for producing Pb-212 and Ac-225 isotopes is disclosed. The method comprises irradiating a Ra-226 containing target with charged particles and/or photons for producing at least Ac-225 isotopes and Ac-224 isotopes. The method further comprises after a cooling time, applying chromatography for separating actinium from the remaining fraction containing radium. The method also comprises, after a first further waiting time, applying extraction chromatography using a resin having an 18-crown-6 ether or an equivalent of an 18-crown-6 ether, as extractant in HNO3 and/or HCl for separating Pb from the remaining fraction containing radium.
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
G21G 1/10 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by bombardment with electrically-charged particles
A method for purifying Ac from a mixture includes Ac and at least one element selected from Ra, Pb, Po, Bi and La. The method includes the steps of: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin).
C22B 60/02 - Obtaining thorium, uranium or other actinides
C22B 7/00 - Working-up raw materials other than ores, e.g. scrap, to produce non-ferrous metals or compounds thereof
B01D 15/18 - Selective adsorption, e.g. chromatography characterised by constructional or operational features relating to flow patterns
B01D 15/42 - Selective adsorption, e.g. chromatography characterised by the development mode, e.g. by displacement or by elution
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
INSTITUT NATIONAL DES RADIOELEMENTS - I.R.E. (Belgium)
Inventor
Cea, Andrew Ken
Leenaers, Ann Josefine Georgette
Pardoen, Thomas
Van Den Berghe, Sven
Host, Valery Claude Lino G.
Wylock, Christophe
Abstract
A nuclear fuel, the nuclear fuel comprising uranium aluminide grains, wherein the uranium aluminide grain properties are selected for good isotope extraction after irradiation and chemical digestion.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
11.
METHODS AND SYSTEMS FOR THE PRODUCTION OF ISOTOPES
A method for producing Pb-212 and Ac-225 isotopes is disclosed. The method comprises irradiating a Ra-226 containing target with charged particles and/or photons for producing at least Ac-225 isotopes and Ac-224 isotopes. The method further comprises after a cooling time, applying chromatography for separating actinium from the remaining fraction containing radium. The method also comprises, after a first further waiting time, applying extraction chromatography using a resin having an 18-crown-6 ether or an equivalent of an 18-crown-6 ether, as extractant in HNO3 and/or HCl for separating Pb from the remaining fraction containing radium.
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
G21G 1/10 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by bombardment with electrically-charged particles
12.
METHODS AND SYSTEMS FOR THE PRODUCTION OF ISOTOPES
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
G21G 1/10 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes outside of nuclear reactors or particle accelerators by bombardment with electrically-charged particles
In a first aspect, the present invention relates to a method for purifying Ac from a mixture comprising Ac and at least one element selected from Ra, Pb, Po, Bi and La, the method comprising: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin).
B01D 11/04 - Solvent extraction of solutions which are liquid
B01D 15/18 - Selective adsorption, e.g. chromatography characterised by constructional or operational features relating to flow patterns
C22B 60/02 - Obtaining thorium, uranium or other actinides
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
In a first aspect, the present invention relates to a method for purifying Ac from a mixture comprising Ac and at least one element selected from Ra, Pb, Po, Bi and La, the method comprising: (a) performing a first separation using a first extraction chromatographic column based on a first resin (either a diglycolamide resin or a dialkylphosphoric acid resin) and a first matrix solution; and (b) performing a second separation using a second extraction chromatographic column based on a second resin (respectively either a dialkylphosphoric acid resin or a diglycolamide resin).
B01D 15/18 - Selective adsorption, e.g. chromatography characterised by constructional or operational features relating to flow patterns
C22B 60/02 - Obtaining thorium, uranium or other actinides
G21G 1/00 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes
B01D 11/04 - Solvent extraction of solutions which are liquid
The present invention describes a membrane mask for immobilization of a region of interest during radiation therapy. The mask comprises at least one material forming a matrix, and at least one radiation-sensitive material integrated as micro- or nano-sized material elements in or onto the matrix. The radiation-sensitive material advantageously provides the possibility of using the mask for performing dosimetry. Use of the mask and a method for performing dosimetry also are described.
The present invention describes an axial pump for pumping liquid metal, the axial pump comprising an inlet for receiving liquid, at least one rotor, the rotor comprising a rotor hub and a plurality of rotor blades positioned thereon, a stator, comprising a stator hub and a plurality of stator vanes, and an outlet for discharging the liquid metal, the pump being adapted for providing efficient pumping while reducing or avoiding erosion of the pump by the liquid metal.
F04D 7/06 - Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type the fluids being hot or corrosive, e.g. liquid metal
F04D 29/52 - CasingsConnections for working fluid for axial pumps
A method for manufacturing a thorium oxide comprising material is described. The method comprising obtaining the thorium oxide comprising material, and sintering the thorium oxide comprising material, whereby at least during the sintering of the sintering process aluminum oxide is present as a sintering assisting additive. A resulting thorium oxide comprising material and a nuclear fuel comprising such material also are disclosed.
A method for producing a MAX phase material with general formulation Mn+1AXn-y is disclosed. Thereby M is a transition metal, A is an A-group element and X is carbon (C) and/or nitrogen (N), where the M, A and X position can be occupied by more than 1 element with n being in the range 1 to 3, y being within the range -0.5 to 0.5. The method comprises providing a starting powder said starting powder comprising least one starting hydride powder, compacting the starting powder and producing the MAX phase material by using a pressure assisted sintering technique. Preferably Zr, Hf, Ti, Nb and Ta are used for M and Si, Sn, Pb, Bi and Al for A.
C04B 35/56 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxides based on carbides
C04B 35/626 - Preparing or treating the powders individually or as batches
The present invention relates to a personal radiation dosimeter (1) for estimating an effective dose of an adult human wearing a radio protective garment. The dosimeter comprises a structural support element (2) for attaching to the radio protective garment while worn and at least two ionizing radiation detectors (5,6) having different dose responses as a function of energy and angle of incidence with respect to a reference direction (4). A predetermined linear combination of the dose responses of the detectors corresponds to an estimate in the range of 40% to 160% of the effective dose received by the adult human under each of a plurality of reference exposures that comprise respectively planar photon wave exposures along the reference direction (4), at an angle of 45° and at an angle of 60° with the reference direction, wherein each wave has an energy distribution corresponding to the W-80, W- 60 or N-60 quality of ISO 4037-1.
A system (100) for measuring mechanical strain. The system comprises a main spring (113) and a connecting piece (114) both with an open concave cross-section, the connecting piece is rotatable mountable inside the main spring at a fixing point (117), such that the respective open concave cross-sections are in the same plane and the open parts are oriented in the same direction. The legs of the main spring (113) are connectable with the specimen shoulders for applying the tips of the measuring arms onto the gauge length of the specimen. Measuring arms (123, 124) are rotatably mountable on the legs of the connecting piece (114) so as to push against the specimen when mounted and so as to rotate when the measured object is subject to strain.
G01B 5/30 - Measuring arrangements characterised by the use of mechanical techniques for measuring the deformation in a solid, e.g. mechanical strain gauge
G01N 3/06 - Special adaptations of indicating or recording means
The present invention describes a membrane mask for immobilization of a region of interest during radiation therapy. The mask comprises at least one material forming a matrix, and at least one radiation-sensitive material integrated as micro- or nano-sized material elements in or onto the matrix. The radiation-sensitive material advantageously provides the possibility of using the mask for performing dosimetry. Use of the mask and a method for performing dosimetry also are described.
Non-invasive in-situ radiation dosimetry A system (1) for measuring radiation dose comprises an excitation device (4) adapted for directing an energy wave (5) at a volume of a substance comprising gas-filled microparticles (3), a detector (7) for detecting a response signal (6) emitted and/or modified from the volume of the substance (2) comprising gas-filled microparticles (3); and a control unit (8). The control unit (8) is adapted for calculating a dose of ionizing radiation previously received by the volume of the substance (2) based on the response signal (6). The invention also relates to a method for measuring a received dose of ionizing radiation and the use of the contrast agent (2) for non-invasive in-situ dosimetry. + FIG.
A method is described for producing nuclear fuel products, the method comprising receiving metallic or intermetallic uranium-based fuel particle cores, providing at least one physical vapour deposited coating layer surrounding the fuel particle core and embedding the nuclear fuel particles in a matrix so as to form a powder mixture of matrix material and coated fuel particles. The at least one physical vapour deposited coating layer may comprise inhibitors of inhibiting, stabilizing and/or reducing interaction between metallic or intermetallic uranium-based fuel particles cores and the matrix wherein the fuel particles typically may be embedded. Alternatively or in addition thereto the deposited coating layer may comprise neutron poisons. The present invention also relates to coated fuel particles, fuel elements and the use of fuel particles for generating neutrons.
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
SCK.CEN (Belgium)
Inventor
Oriol, Ludovic
Lescop, Bernard
Vermeeren, Ludo
Abstract
The invention relates to a device for the in-line measurement of a flow of rapid epithermal neutrons, characterised in that the device includes: a rapid epithermal neutron detector (DNR) capable of mainly detecting rapid epithermal neutrons; a thermal neutron detector (DNT) capable of mainly detecting thermal neutrons; a first processing circuit (C1) for processing the signal supplied by the rapid neutron detector; a second processing circuit (C2) for processing the signal output by the thermal neutron detector; a means (CE, PPM) capable of determining the evolutive sensitivity to rapid neutrons and thermal neutrons of each of the neutron detectors; and a computer (CALC) for calculating the rapid and epithermal neutron flow from said evolutive sensitivities and from the signal supplied by the first and second processing circuits.
patents
