Abstract: This disclosure concerns a new method for preparing radioisotopes, such as molybdenum-99, by alpha particle irradiation, such as by alpha particle irradiation of zirconium-96. Molybdenum-99 is a precursor to the medically-significant radioisotope technetium-99m. Also disclosed are novel compositions containing one or more of technetium-99m, molybdenum-99 and zirconium species. Systems for producing molybdenum-99 and technetium-99m, including alpha particle generators and irradiation targets, also are described.
Type:
Grant
Filed:
August 2, 2005
Date of Patent:
February 28, 2012
Assignee:
Battelle Memorial Institute
Inventors:
Robert E. Schenter, Dennis W. Wester, Glenn W. Hollenberg, Brian M. Rapko, Gregg J. Lumetta
Abstract: The invention relates to a manufacturing facility comprising a building structure which encloses working space of the manufacturing facility, the building structure being designed to house a cyclotron and to be transportable by truck or rail to a destination site, wherein the manufacturing facility, except for lacking a cyclotron during transport, is substantially equipped during transport to produce and package a radiopharmaceutical. The invention also relates to a method of providing a manufacturing facility for producing a radioactive material, the method comprising the steps of designing the manufacturing facility to receive a cyclotron; equipping the manufacturing facility with a synthesis unit which is designed to receive a first radioactive material from the cyclotron and to produce a second radioactive material; transporting the manufacturing facility to a site; transporting the cyclotron to the site; and enclosing the cyclotron inside the manufacturing facility.
Abstract: A spallation device for production of neutrons includes a spallation target that produces neutrons by interaction with a hollow particle beam propagating within a first chamber, a second chamber containing the spallation target, and a leak tight partition separating the first and second chambers. The spallation device is particularly applicable to basic physics, medicine, and transmutation.
Abstract: Flow of mercury from a liquid-heavy-metal inflow port toward an inner forward end of a container body is rectified by a plurality of incoming-passage guide vanes in a liquid-heavy-metal incoming passage. Flow of the mercury from the forward end of the container body toward a liquid-heavy-metal outflow port is rectified by a plurality of return-passage guide vanes in a liquid-heavy-metal return passage. As a result, occurrence of stagnation and/or recirculation flows of the mercury in the container body is suppressed and a steady and highly uniform stream of the mercury is formed throughout in the container body. The container body is covered with a container outer shell to prevent any leakage of the mercury to outside due to a damage of the container body.
Type:
Grant
Filed:
February 8, 2000
Date of Patent:
November 5, 2002
Assignees:
Agency of Industrial Science and Technology Japan Atomic
Energy Research Institute, Ishikawajima-Harima Jukogyo Kabushiki Kaisha
Abstract: A target grid assembly for employment in a target assembly used to produce radioisotopes by bombarding a target material contained in the target assembly with a particle beam. The target assembly includes the target grid assembly, the target window and a target body enclosed in a target housing. The target body defines a target reservoir for receiving the target material and the target window serves to seal the target reservoir.
The target grid assembly includes a vacuum window and a target grid. The target grid defines a target grid portion, a helium input and a helium output. The target grid portion defines a plurality of target grid supports which are configured to form a plurality of target grid oblong openings. The vacuum window is supported against the upstream side of the target grid portion and the target window is supported between the downstream side and the target body.
Abstract: A stand-alone low-voltage direct current power supply, for use as a battery, which is energized by the decay of a radioactive isotope in response to neutron capture. During this decay, either .alpha.- or .beta.-particles are emitted. The emitting radioactive isotope should have adequate half-life and no .gamma.-emission. The preferred .beta.-emitting radioisotope is thallium, which decays directly to the ground state of Pb.sup.204 by 763-keV .beta.-decay with no .gamma.-emission. The resulting .beta.-particles are collected to form a current which can be used for various purposes inside a reactor. The preferred .alpha.-emitting radioisotope is americium.
Abstract: A process for producing radionuclides using a porous carbon target. The process includes the steps of inserting a porous carbon target with tailored solid and void dimensions in the path of a bombarding beam; introducing fluid into the porous carbon target; bombarding the porous carbon target to produce at least one type of radionuclide; collecting the fluid and separating the resulting radionuclides.
Abstract: A radioisotope production facility (12) produces radioisotopes having application to Positron Emission Tomography. The radioisotopes produced include .sup.18 F, .sup.13 N, .sup.15 O, and .sup.11 C, and are produced by irradiating a selected target material (40) with a high energy .sup.3 He.sup.++ beam accelerated in a radio frequency quadruple (RFQ) linear accelerator (34). The facility includes, in addition to the RFQ linear accelerator and the selected target, a source of .sup.3 He.sup.++ ions (30), low energy transport means (32) for focusing the .sup.3 He.sup.++ beam into the RFQ linear accelerator, and a high energy transport means (36) for directing the accelerated .sup.3 He.sup.++ beam at the selected target. Further included is a target subsystem (16) that holds the target, automatically prepares precursors containing the .sup.18 F, .sup.13 N, .sup.15 O, and .sup.
Type:
Grant
Filed:
March 14, 1989
Date of Patent:
August 6, 1991
Assignee:
Science Applications International Corporation