摘要:
A method of preparing radioisotope hybrid nanocomposite particles using a sol-gel reaction, and radioisotope hybrid nanocomposite particles prepared using the same are provided. The method includes preparing a complex precursor using a metal ion and an unshared electron pair reactive compound, growing hybrid nanocomposite particles based on the complex precursor by means of a sol-gel reaction, calcining the nanocomposite particles in the air to remove organic matters present in the nanocomposite particles, and irradiating the nanocomposite particles with neutrons to prepare radioisotope hybrid nanocomposite particles. The radioisotope nanocomposite particles prepared using the method can be used as diagnostic and therapeutic particles in the fields of oil refining, chemistry, cement, agriculture, water resources, environment, ocean, and medicine, and can also be used as a radioisotope tracer for evaluating the risk of nanomaterials.
摘要:
Methods of synthesizing 100Mo2C and 99mTcO4− are disclosed. Methods of 100Mo2C generation involve thermally carburizing 100MoO3. Methods of 99mTcO4 generation involve proton bombardment of 100Mo2C in a cyclotron. Yields of 99mTcO4 can be increased by sintering 100Mo2C prior to bombardment. The methods also include recycling of 100Mo2C to form 100MoO3. SPECT images obtained using 99mTcO4 generated by the disclosed methods are also presented.
摘要:
An isotope production target may include an outer diameter wall and an inner diameter wall. An isotope source may be located between the inner diameter wall and the outer diameter wall, and the isotope source may comprise fissile material interspersed with one or more voided regions. A central region may be located within the inner diameter wall, and the central region may be configured to house a neutron thermalization volume.
摘要:
The present disclosure generally relates to methods and structures for the production of radioisotopes from the thermal neutron irradiation of selected natural isotopes. The methods, structures and operations are applicable to the production of any radioisotope that may be produced from neutron irradiation.
摘要:
The present invention relates generally to a system and method for producing Technetium-99m. More specifically, the present invention relates to a novel method and device for modifying commercially-available, widely-used low energy positron emission tomography (PET) cyclotrons in order to produce Technetium-99m in a more efficient, less expensive manner that previously known.
摘要:
The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n),whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided.
摘要:
At least one system for eluting a radioactive material and a method of eluting a radioactive material is provided. The system for eluting a radioactive material may include an elution column configured to enclose an radioactive material, a first sealing member sealing a first end of the elution column, a second sealing member sealing a second end of the elution column, an elution supply source connected to the first end of the elution column via a first needle, a collection system connected to the second end of the elution column via a second needle, and a filter in the elution column, the filter being configured to support the radioactive material and prevent the radioactive material from contacting the second needle.
摘要:
The present invention relates to an universal method for the large scale production of high-purity carrier free or non carrier added radioisotopes by applying a number of “unit operations” which are derived from physics and material science and hitherto not used for isotope production. A required number of said unit operations is combined, selected and optimized individually for each radioisotope production scheme. The use of said unit operations allows a batch wise operation or a fully automated continuous production scheme. The radioisotopes produced by the inventive method are especially suitable for producing radioisotope-labelled bioconjugates as well as particles, in particular nanoparticles and microparticles.
摘要:
The invention provides a method using accelerators to produce radio-isotopes in high quantities. The method comprises: supplying a “core” of low-enrichment fissile material arranged in a spherical array of LEU combined with water moderator. The array is surrounded by substrates which serve as multipliers and moderators as well as neutron shielding substrates. A flux of neutrons enters the low-enrichment fissile material and causes fissions therein for a time sufficient to generate desired quantities of isotopes from the fissile material. The radio-isotopes are extracted from said fissile material by chemical processing or other means.
摘要:
Example embodiments are directed to materials useable as burnable poisons in nuclear reactors, components using the same, and methods of using the same. Example embodiment burnable poison materials produce desired daughter products as they burn out, thereby permitting placement and use for neutronic characteristic improvement and/or neutron flux shielding in locations conventionally barred as uneconomical. Example embodiment burnable poison materials may include natural iridium and enriched iridium-193. Example embodiment components may be fabricated, shaped, and placed to provide desired burnable poison effects in the reactor core in conventional locations and locations not conventionally used due to economic infeasibility. Example methods include use of example embodiment components, including determining locations benefiting from burnable poison effects, fabricating example embodiment components of a desired amount of example embodiment burnable poison materials, placing the example embodiment components, exposing example embodiment components to flux within the operating nuclear reactor, removing and harvesting example embodiment burnable poison components for desired daughter products produced from example embodiment burnable poison materials.