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630 results about "Radioactive decay" patented technology

Radioactive decay (also known as nuclear decay, radioactivity, radioactive disintegration or nuclear disintegration) is the process by which an unstable atomic nucleus loses energy (in terms of mass in its rest frame) by radiation, such as an alpha particle, beta particle with neutrino or only a neutrino in the case of electron capture, or a gamma ray or electron in the case of internal conversion. A material containing unstable nuclei is considered radioactive. Certain highly excited short-lived nuclear states can decay through neutron emission, or more rarely, proton emission.

Microfluidic chip capable of synthesizing radioactively labeled molecules on a scale suitable for human imaging with positron emission tomography

Described herein are automated, integrated microfluidic device comprising a chemical reaction chip comprising for performing chemical reaction, a microscale column integrated with the chip and configured for liquid flow from the column to at least one flow channel, and wherein the fluid flow into the column is controlled by on-chip valves; and comprising at least two on-chip valves for controlling fluid flow in the microfluidic device.
Owner:SIEMENS MEDICAL SOLUTIONS USA INC +1

Microspheres capable of binding radioisotopes, optionally comprising metallic microparticles, and methods of use thereof

One aspect of the present invention relates to a microsphere, comprising a hydrophilic polymer comprising a plurality of pendant anionic groups; a transition-metal, lanthanide or group 13-14 metal oxide, polyoxometalate or metal hydroxide or combination thereof; and a first radioisotope that emits a therapeutic β-particle. In certain embodiments, the microsphere further comprsies a second radioisotope that emits a diagnostic γ-ray; wherein the atomic number of the first radioisotope is not the same as the atomic number of the second radioisotope. In certain embodiments, the microsphere is composed of polymer impregnated with zirconia bound to 32p as the source of the therapeutic β-emissions and 67Ga as the source of the diagnostic γ-emissions. Another aspect of the present invention relates to the preparation of a microsphere impregnated with a radioisotope that emits therapeutic β-particles and a radioisotope that emits diagnostic β-emitting radioisotope and a γ-emitting radioistope; wherein the atomic number of the first radioisotope is not the same as the atomic number of the second radioisotope. In certain embodiments, said microspheres are administered to the patient through a catheter. In another embodiment, the microsphere is combined with the radioisotopes at the site of treatment.
Owner:BIOSPHERE MEDICAL INC

Assembly for transmutation of a long-lived radioactive material

A new transmutation assembly permits an efficient transmutation of a long-lived radioactive material (long-lived FP nuclides such as technetium-99 or iodine-129) which was produced in the nuclear reactor. Wire-type members of a long-lived radioactive material comprised of metals, alloys or compounds including long-lived FP nuclides are surrounded by a moderator material and installed in cladding tubes to form FP pins. The FP pins, and nothing else, are housed in a wrapper tube to form a transmutation assembly. The wire-type members can be replaced by thin ring-type members. The transmutation assemblies can be selectively and at least partly loaded into a core region, a blanket region or a shield region of a reactor core in a fast reactor. From a viewpoint of reducing the influence on the reactor core characteristics, it is optimal to load the transmutation assemblies into the blanket region.
Owner:JAPAN ATOMIC ENERGY AGENCY INDEPENDANT ADMINISTRATIVE CORP

Multimodal silica-based nanoparticles

The present invention provides a fluorescent silica-based nanoparticle that allows for precise detection, characterization, monitoring and treatment of a disease such as cancer. The nanoparticle has a range of diameters including between about 0.1 nm and about 100 nm, between about 0.5 nm and about 50 nm, between about 1 nm and about 25 nm, between about 1 nm and about 15 nm, or between about 1 nm and about 8 nm. The nanoparticle has a fluorescent compound positioned within the nanoparticle, and has greater brightness and fluorescent quantum yield than the free fluorescent compound. The nanoparticle also exhibits high biostability and biocompatibility. To facilitate efficient urinary excretion of the nanoparticle, it may be coated with an organic polymer, such as poly(ethylene glycol) (PEG). The small size of the nanoparticle, the silica base and the organic polymer coating minimizes the toxicity of the nanoparticle when administered in vivo. In order to target a specific cell type, the nanoparticle may further be conjugated to a ligand, which is capable of binding to a cellular component associated with the specific cell type, such as a tumor marker. In one embodiment, a therapeutic agent may be attached to the nanoparticle. To permit the nanoparticle to be detectable by not only optical fluorescence imaging, but also other imaging techniques, such as positron emission tomography (PET), single photon emission computed tomography (SPECT), computerized tomography (CT), bioluminescence imaging, and magnetic resonance imaging (MRI), radionuclides / radiometals or paramagnetic ions may be conjugated to the nanoparticle.
Owner:SLOAN KETTERING INST FOR CANCER RES +1

Fully-automated microfluidic system for the synthesis of radiolabeled biomarkers for positron emission tomography

The present application relates to microfluidic devices and related technologies, and to chemical processes using such devices. More specifically, the application discloses a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in a fast, efficient and compact manner. In particular, this application describe an automated, stand-alone, microfluidic instrument for the multi-step chemical synthesis of radiopharmaceuticals, such as probes for PET and a method of using such instruments.
Owner:SIEMENS MEDICAL SOLUTIONS USA INC

Long life high efficiency neutron generator

The design of a compact, high-efficiency, high-flux capable compact-accelerator fusion neutron generator (FNG) is discussed. FNG's can be used in a variety of industrial analysis applications to replace the use of radioisotopes which pose higher risks to both the end user and national security. High efficiency, long lifetime, and high power-handling capability are achieved though innovative target materials and ion source technology. The device can be scaled up for neutron radiography applications, or down for borehole analysis or other compact applications. Advanced technologies such as custom neutron output energy spectrum, pulsing, and associated particle imaging can be incorporated.
Owner:STARFIRE IND LLC

Nuclear Assisted Hydrocarbon Production Method

A method is disclosed for the temporary or permanent storage of nuclear waste materials comprising the placing of waste materials into one or more repositories or boreholes constructed into an unconventional oil formation. The thermal flux of the waste materials fracture the formation, alters the chemical and / or physical properties of hydrocarbon material within the subterranean formation to allow removal of the altered material. A mixture of hydrocarbons, hydrogen, and / or other formation fluids are produced from the formation. The radioactivity of high-level radioactive waste affords proliferation resistance to plutonium placed in the periphery of the repository or the deepest portion of a borehole.
Owner:BAIRD JAMES RUSSELL

Proton accelerator complex for radio-isotopes and therapy

A complex of proton accelerators, includes the following functionally interconnected components: a proton source, a cyclotron, at least one target, located either internally or externally to the cyclotron, a medium energy beam transport magnetic channel, a radiofrequency linear accelerator, a high energy beam transport channel towards an area dedicated to the irradiation of tumors with proton beams, as well as a modular system for supplying radio frequency power capable of feeding, independently two or more accelerating modules of the linac. An integrated computerized system controls the complex of accelerators so to carry out, either in alternation or simultaneously, both the production of radioisotopes—for medical, industrial and therapeutical purposes—and the therapeutical irradiation of, even deep seated tumors. The complex of accelerators produces proton beams which, applying the recently developed ‘spot scanning’ technique, are more suited for the tumor irradiation than the ones produced by cyclotrons and synchrotrons.
Owner:FOND PER ADROTERAPIA ONCOLOGICA TERA

Apparatus and method for high dose rate brachytherapy radiation treatment

A method and apparatus for the in vivo location and tracking of a radioactive seed source during and after brachytherapy treatment. The method comprises obtaining multiple views of the seed source in a living organism using: 1) a single PSPMT detector that is exposed through a multiplicity of pinholes thereby obtaining a plurality of images from a single angle; 2) a single PSPMT detector that may obtain an image through a single pinhole or a plurality of pinholes from a plurality of angles through movement of the detector; or 3) a plurality of PSPMT detectors that obtain a plurality of views from different angles simultaneously or virtually simultaneously. The plurality of images obtained from these various techniques, through angular displacement of the various acquired images, provide the information required to generate the three dimensional images needed to define the location of the radioactive seed source within the body of the living organism.
Owner:JEFFERSON SCI ASSOCS LLC

Storing type photo-ionisation ion migration mass spectrum

The invention relates to a storage photoionization ion migration mass spectrum, mainly solving the problems of the complex line spectrum measured and weaker signals obtained by adopting radioactive component as ionization source. It includes acceleration grid electrode, ionization light source, sampling mouth, ionization region, drift region and ion collecting plate, and its character: the ionization light source is vacuum ultraviolet lamp, it sets an ion storage region structure between the ionization and drift regions to replace the ion gate. It has ion storing function, largely enhances monitoring sensitivity, clear migration mass spectrum chart of the matter to be measured, reduces influence of noise and enhances collecting efficiency.
Owner:ANHUI INST OF OPTICS & FINE MECHANICS - CHINESE ACAD OF SCI

Sustainable Modular Transmutation Reactor

A light water reactor to safely convert depleted uranium into a fuel source that could be used as a sustainable source of energy for centuries. The reactor is a type of breed-burn reactor uniquely combined with a proliferation-resistant fuel cycle with no uranium enrichment and no plutonium isolation. It is comprised of a compact factory-produced fast region and a thermal region that produces about 95% of the core power and contains the passageways for transports of delayed-neutron emitters to the fast region, where they can provide additional neutrons (source-based mode) or all the necessary excitation without an external neutron source (self-regulating mode). A second embodiment of the invention is a small unit driven by a neutron source with beam recycling for propulsion, electrical power or radioisotope production. It could also serve as a demonstration facility for the transmutation reactor with fission-fusion fuel.
Owner:BLANOVSKY ANATOLY

Methods and computer readable medium for improved radiotherapy dosimetry planning

Methods and computer readable media are disclosed for ultimately developing a dosimetry plan for a treatment volume irradiated during radiation therapy with a radiation source concentrated internally within a patient or incident from an external beam. The dosimetry plan is available in near"real-time" because of the novel geometric model construction of the treatment volume which in turn allows for rapid calculations to be performed for simulated movements of particles along particle tracks therethrough. The particles are exemplary representations of alpha, beta or gamma emissions emanating from an internal radiation source during various radiotherapies, such as brachytherapy or targeted radionuclide therapy, or they are exemplary representations of high-energy photons, electrons, protons or other ionizing particles incident on the treatment volume from an external source. In a preferred embodiment, a medical image of a treatment volume irradiated during radiotherapy having a plurality of pixels of information is obtained.
Owner:BATTELLE ENERGY ALLIANCE LLC

Structure steel material suitable for fusion reactor

A structural steel material is suitable to fusion reactor, it is a martensite steel with low activation and is composed of element Fe, and it also contains the alloys Cr, W, V, Ta, Mn and C. It is suitable to use in the fusion reactor which has the resistance against the irradiation. The recipe of this steel replaces the elements Mo, Nb and Ni which are contained in the normal steels with W, Ta, V and Mn, so it assures the characteristic of low activation. Through optimization of the ingredients, the main nature of the steel increases. At the same time we strictly control the lever of long nuclear lifetime radioactive impurity which is created by irradiation with neutron. The half-life of the radioactive species which activated by irradiation with neutron is short, and the lever can be decreased to lower than the operational lever 10mSv / h in 100 years.
Owner:INST OF PLASMA PHYSICS CHINESE ACAD OF SCI

Detection of neutrons and heavy charged particles

The present invention provides a method and system for measuring the spatial distribution of fluorescence from the excited radiochromic luminescent material; and for signal processing of the spatial distribution of fluorescence to thereby detect tracks of one or more heavy charged particles with which the luminescent material has been irradiated. The present invention also provides a method and system for measuring the spatial distribution of fluorescence from an excited radiochromic luminescent material that has been irradiated with a hot particle of a radioactive material. The present invention provides a method for detecting thermal and fast neutrons as well as a method for determining parameters of heavy charge particles. In several embodiments of the present invention, the luminescent material comprises Al2O3 doped with magnesium and carbon.
Owner:LANDAUER INC

Irradiation target retention assemblies for isotope delivery systems

Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.
Owner:GE HITACHI NUCLEAR ENERGY AMERICAS

Small neutron source adopting windowless gas target

InactiveCN101916607ANo handlingNo loop issuesNeutron sourcesNeutron yieldHigh pressure
The invention discloses a small neutron source adopting a windowless gas target, which belongs to the field of nuclear technology and application. In the invention, an ECR (Electron Cyclotron Resonance) ion source is used for generating a deuterium ion and directly extracted by a high-voltage extraction electrode for bombarding a windowless gas target sealed by a plasma; because the windowless deuterium gas target is sealed by adopting the plasma, the windowless deuterium gas target is allowed to bear high-flow-strength beam current; and because the energy loss of the deuterium ion when penetrating through a plasma window is less, the neutron yield is higher. Compared with a neutron pipe, the neutron source provided by the invention has high allowed beam current strength and high neutron yield. Compared with an accelerator neutron source with large size, complex system and high cost, the neutron source provided by the invention has small size, simple system and low cost. Compared with a neutron source for directly carrying out deuterium-tritium reaction on an ion source to generate neutron, the ion source has simple system, low cost and no tritium radioactive processing and circulating problem. The invention has very wide application prospect.
Owner:PEKING UNIV

Semi-chromatography gamma scanning method for low-medium radioactive waste barrel measurement

The invention provides a semi-chromatography gamma scanning method for low-medium radioactive waste barrel measurement. A rotary platform, a detector platform, a detector with a collimator, a transmission source platform, a transmission source, a shielding part of the transmission source and an analysis module are adopted in the method. A waste barrel is divided into multiple section layers in the height direction, the waste barrel is rotated, surface distribution of radioactive point sources on the section layers is changed into linear distribution of ring sources in the radius direction, the detector conducts measurement at different section layer heights and different eccentric positions in the section layers, an equation set reflecting the mutual relation between the detector counting rate and the activity of nuclide in annular grids is established, the equation set is solved, distribution of the activity of the radioactive nuclide in the waste barrel in the diameter direction and the height direction of the barrel is acquired, and the total activity of the radioactive nuclide in the waste barrel is acquired through summation. The method is high in measurement accuracy, short in measurement time and high in practical value and application prospect.
Owner:SHANGHAI JIAO TONG UNIV

Radioactive particles and methods for preparing same

A nuclear medical drug for localize radiotheraphy of a tumor and methods for its preparation. The drug includes a radioactive ceramic or glass particle having biocompatiblity. Ceramic or glass particles prepared by traditional processes become radioactive particles with pure beta -particle-emitting radionuclides after being irradiated with an appropriate flux of neutrons. The radioactive particle with suitable particle size can then be dispersed into a contrast medium for injection or can be implanted by operation.
Owner:DEPT OF HEALTH THE EXECUTIVE YUAN REPUBLIC OF CHINA

Apparatuses and methods for production of radioisotopes in nuclear reactor instrumentation tubes

Example embodiments are directed to apparatuses and methods for producing radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable from nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes.
Owner:GE HITACHI NUCLEAR ENERGY AMERICAS

Method and apparatus for producing radioactive materials for medical treatment using x-rays produced by an electron accelerator

An apparatus and method for irradiating target objects, especially medical stents for in vivo implantation. A linear accelerator provides a high energy electron beam that impinges upon and is received by an x-ray conversion target. The x-ray conversion target is activated by either a static or dynamically moveable electron beam to generate and emit an x-ray flux so as to efficiently intercept the target object. The x-ray flux is directed to the target object for a desired time period and is of sufficiently high energy to efficiently impart radioactive properties to the target object. Alternatively, the target object is positioned within the path of the x-ray flux or is translated within the path during irradiation. Mechanical transport assemblies such as a carousel, rotational and / or linear translator and / or movement tube system also may be provided.
Owner:VARIAN MEDICAL SYSTEMS

Aflatoxin degradation method

The invention discloses a method for degrading aflatoxin, which makes use of gamma rays to irradiate a sample containing the aflatoxin, wherein the gamma rays are generated by a radioactive substance Co, and the irradiation dose is between 0 and 10 kGy not including 0, preferably between 2 and 10 kGy, more preferably between 4 and 10 kGy, particularly preferably between 6 and 10 kGy, and the most preferably 10 kGy. The sample containing the aflatoxin is a farm product containing the aflatoxin or a product obtained by processing the farm product, such as food, feedstuff, and the like. The method is particularly applicable to degrading the aflatoxin B1, not only can kill pathogenic microorganisms but also can degrade biotoxin therein, and does not generate any industrial pollution.
Owner:INST OF AGRO FOOD SCI & TECH CHINESE ACADEMY OF AGRI SCI

Inorganic Nanoparticles of High Density to Destroy Cells In-Vivo

The present application relates to novel excitable particles which can be used in the health sector. It more particularly relates to particles which can generate electrons and / or high energy photon when excited by ionizing radiations such as X- Rays, γ-Rays, radioactive isotope and / or electron beams, and to the uses thereof in health, in particular in human health. The inventive particles are made of an inorganic material comprising oxygen, in particular an oxide, said material having an adequate density, and can be activated in vitro, ex vivo, or in vivo, by controllable external excitation, in order to disturb, alter or destroy target cells, tissues or organs. The invention also relates to methods for the production of said particles, and to pharmaceutical or medical device compositions containing same.
Owner:NANOBIOTIX SA

Apparatus and method for controllable downhole production of ionizing radiation without the use of radioactive chemical isotopes

Apparatus for the controllable downhole production of ionizing radiation (12), the apparatus including at least a thermionic emitter (11) which is arranged in a first end portion (7a) of an electrically insulated vacuum container (9), and a lepton target (6) which is arranged in a second end portion (7b) of the electrically insulated vacuum container (9); the thermionic emitter (11) being connected to a series of serially connected negative electrical-potential-increasing elements (141, 142, 143, 144), each of said electrical-potential-increasing elements (141, 142, 143, 144) being arranged to increase an applied direct-current potential (δV0, δV1, δV1+2, . . . , δV1+2+3) by transforming an applied, driving voltage (VAC), and to transmit the increased, negative direct-current potential (δV1, δV1+2, . . . , δV1+2+3+4) and also the driving voltage (VAC) to the next unit in the series of serially connected elements (141, 142, 143, 144,5), and the ionizing radiation (12) exceeding 200 keV with a predominant portion of the spectral distribution within the Compton range.
Owner:VISURAY TECH

Radioluminescent Phototherapy Eye Device

Embodiments of the present disclosure are directed to a phototherapy eye device. In an example, the phototherapy eye device includes a number of radioluminescent light sources and an anchor. Each radioluminescent light source includes an interior chamber coated with phosphor material, such as zinc sulfide, and containing a radioisotope material, such as gaseous tritium. The volume, shape, phosphor material, and radioisotope material are selected for emission of light at a particular wavelength and delivering a particular irradiance on the retina (when implanted in an eyeball). The wavelength is in the range of 400 to 600 nm and the irradiance is substantially 109 to 1011 photons per second per cm2.
Owner:CALIFORNIA INST OF TECH

High power high yield target for production of all radioisotopes for positron emission tomography

A high power high yield target for the positron emission tomography applications is introduced. For production of Curie level of Fluorine-18 isotope from a beam of proton it uses about one tenth of Oxygen-18 water compared to a conventional water target. The target is also configured to be used for production of all other radioisotopes that are used for positron emission tomography. When the target functions as a water target the material sample being oxygen-18 or oxygen-16 water is heated to steam prior to irradiation using heating elements that are housed in the target body. The material sample is kept in steam phase during the irradiation and cooled to liquid phase after irradiation. To keep the material sample in steam phase a microprocessor monitoring the target temperature manipulates the flow of coolant in the cooling section that is attached to the target and the status of the heaters and air blowers mounted adjacent to the target. When the target functions as a gas target the generated heat from the beam is removed from the target by air blowers and the cooling section. The rupture point of the target window is increased by a factor of two or higher by one thin wire or two parallel thin wires welded at the end of a small hollow tube which is held against the target window. One or two coils are used to produce a magnetic filed along the beam path for preventing the density depression along the beam path and suppression of other instabilities that can develop in a high power target.
Owner:AMINI BEHROUZ

Mixed nuclide gamma point source volume sample efficiency calibration method

InactiveCN103135122AGuarantee the traceability of the quantity valueAvoid complexityX/gamma/cosmic radiation measurmentCalibration resultRadioactive waste
The invention belongs to the ionizing radiation measurement technology, in particular to a mixed nuclide gamma point source volume sample efficiency calibration method. Measurement results of solid mixed nuclide gamma point source around a detector are adopted and the monte carlo simulation calculation is combined to determine the detection efficiency of the detector to arbitrary axisymmetric shape volume samples. Through the measurement results of solid mixed nuclide gamma point source around the detector, a volume sample detection efficiency curve can be determined. Under the premise that the traceability of calibration result values is guaranteed, the problems that complex manufacturing process and occurrence of radioactive wastes which are brought by other calibration methods ( such as standard volume sample calibration) are avoided.
Owner:CHINA INST FOR RADIATION PROTECTION

Ion migration spectrometer based on sample through membrane

An ion migration spectroscope based on film sample feed-in consists of film sample feeding in unit, vacuum ultraviolet ray source, ionizing reaction region, ion gate, ion floating region and receiving electrode.
Owner:上海新漫传感科技有限公司
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