625 results about "Radioactive decay" patented technology

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

In a state in which a subject is absent, blank data is collected by a self-radioactivity element typified by Lu-176 (S1). In a state in which the subject is present, transmission data is collected by the self-radioactivity element (S2). Emission data is collected by γ rays emitted from the subject injected with a radiopharmaceutical (S3). Absorption-corrected data is calculated based on the blank data and the transmission data (S4 to S7), and the emission data is absorption-corrected using the absorption-corrected data (S8). Although such background data obtained by the self-radioactivity is originally abandoned, the background data is rather used for the absorption-corrected data. Stable absorption correction can be thereby conducted.

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.

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.