Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: Target, computer software and method for direct production of 99mTc using small energy accelerators. The method includes positioning a target holder to be bombarded with a beam of protons, the target holder having a target that includes a first hard core layer, a second hard core layer, a third layer of highly enriched 100Mo and a substrate, distributed in this order; bombarding the target with the beam of protons, wherein the protons have an energy between 10 and 35 MeV and a current between 20 and 500 ?A; and terminating the bombarding with the beam of protons after a time interval between half an hour and 8 hours.

Abstract: The present invention provides a system and method for a system for accommodating a solid target in an accelerator. The system and method includes a target changer having at least one port for accommodating the solid target, an insert for receiving the solid target in the target changer, a piston for providing a vacuum and a cooling system for the solid target, a cylinder for displacing the piston in one of three positions; and a bracket for securing the insert, piston and cylinder to the target changer.

Abstract: Example embodiments are directed to tie plate attachments having irradiation targets and/or fuel assemblies having example embodiment tie plate attachments with irradiation targets and methods of using the same to generate radioisotopes. Example embodiment tie plate attachments may include a plurality of retention bores that permit irradiation targets to be contained in the retention bores. Irradiation targets may be irradiated in an operating nuclear core including the fuel assemblies, generating radioisotopes that may be harvested from the spent nuclear fuel assembly by removing example embodiment tie plate attachments.

Abstract: A capsule for holding, irradiating, and eluting a material is provided. Methods of fabricating and using the capsule are also provided. The capsule may include a multidiameter tube with a first end region, a second end region, and a middle region. Washers and filters are provided in the end regions and the end regions may be sealed using various methods and materials with the end caps press fit into the end regions. The middle region is designed to store a material to be irradiated by a neutron flux source. The capsule components may be made from materials having a low nuclear cross section so that the capsule may be handled safely after an irradiation step is performed. The capsule is also designed to have a symmetric configuration as an elution and irradiation column so that the same capsule may be used to elute the material within the middle region of the capsule after an irradiation step is performed.

Abstract: The invention relates to the confinement of an alloy formed of actinide transuranic radioactive wastes and beryllium metal within a neutron moderating and reflecting apparatus to cause accelerated destruction (burning) of the actinide wastes. Waste actinides, including plutonium, neptunium, americium, and curium, emit alpha particles by radioactive decay. The alpha particles are converted into neutrons by the beryllium through an alpha-neutron (alpha, n) reaction. The neutrons developed by the alpha, n reaction are moderated by a surrounding layer of graphite, which allows the slowed neutrons to cause additional fission or decay events within the waste actinide alloy. This process is passive because the alpha particles that initiate the actinide burning are an intrinsic physical property of the actinides.

Abstract: Improvements in both the pressure resistance of a target and the cooling effect of a target liquid can be made compatible, and the boiling of the target liquid is sufficiently suppressed. A radioisotope manufacturing apparatus can include a radiation source which radiates radioactive rays, and a target having a holding unit which holds the target liquid. The holding unit can include a spherical bottom surface which is recessed in a direction away from the radiation source so as to have an apex. The target can be disposed so that the intersection position between a radiation axis of radioactive rays radiated from the radiation source and the bottom surface can be located below the apex.

Abstract: Example embodiments and methods are directed to irradiation target retention devices that may be inserted into conventional nuclear fuel rods and assemblies. Example embodiment devices may hold several irradiation targets for irradiation during operation of a nuclear core containing the assemblies and fuel rods having example embodiment irradiation target retention devices. Irradiation targets may substantially convert to useful radioisotopes upon exposure to neutron flux in the operating nuclear core and be removed and harvested from fuel rods after operation.

Abstract: 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.

Abstract: The present invention relates generally to an apparatus of assembling a capsule for neutron-irradiation experiments. The capsule may contain test specimens to develop nuclear fuel, and may comprise a capsule main body and protection tube that may be assembled and disassembled using separate joining means. The present invention provides a capsule assembling apparatus that may enable safe and easy assembly/disassembly of the capsule placed at a given depth in a working pool through remote working. The capsule assembling apparatus may comprise a base structure loading the capsule main body, a guiding pipe of a given length extending from the base structure to provide a pathway through which the capsule main body is loaded on the base structure, a damper fixing the capsule main body to the guiding pipe, and a coupler coupling the capsule main body with the protection tube.

Abstract: An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H218O, and reduces the deformation of thin sheets to thus increase the durability of the thin sheets. The F-18 production target system includes a frame, which has the shape of a cylinder the central portion of which is bored, holds H218O in the central portion, and includes through-holes bored from the central portion to the outer circumference thereof, thin sheets, which are installed on opposite sides of the frame so as to seal the central portion, and a support, which is installed in the central portion so as to prevent the thin sheets from being deformed.

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: A flexible source wire is provided containing a radioactive source that is capable of maneuvering through a tortuous narrow passage to a treatment site within the body. This source wire includes a thin flexible housing tube, housing therein a flexible backbone wire, wherein both the tube and the wire are constructed from a material exhibiting little or no memory retention when bent. A radioactive core is provided in the proximal end (i.e., the treatment end) of the thin flexible housing tube and abuts the proximal end of the backbone wire. Both ends of the source wire are sealed and the proximal end of the source wire is rounded to allow ease of movement as it travels through the bends and turns in the body.

Abstract: A device for preparing a radioactive water solution to be infused in a patient includes a reaction chamber (13) in which radioactive water vapour is formed by the catalysed reaction of oxygen gas containing oxygen-15 and hydrogen gas. A diffusion chamber (14) is provided which allows the radioactive water to penetrate, but which prevents the penetration of gasses. Tubes (26) and valves (16, 18) direct a sterile saline solution to the diffusion chamber (14), and then direct the saline solution containing radioactive water out from the diffusion chamber to a patient, or to a decay coil (22) being a part of the device. A measuring instrument is provided for measuring the radioactivity of the radioactive solution. The device is characterized in that the diffusion chamber (14), the tubes (26) the valves (16, 18), the radioactivity measuring instrument (17), and preferably also the reaction chamber 913), are mounted in the same frame 50, whereby they form a separate unit i.e.

Abstract: The present invention provides a remote-controlled in-pile creep test system used in in-pile creep tests for measuring and determining mechanical properties of nuclear materials irradiated in research reactors.

Abstract: An instrumented capsule for material irradiation tests in research reactors. The instrumented capsule performs an optimum material irradiation test under a testing environment similar to the operational environment of a real reactor. The capsule minimizes the influence of flow-induced vibration caused by forced-circulation-type coolant flow in a research reactor, and overcomes the problems experienced in the conventional breakable parts of instrumented capsules which may be broken during the process of loading/unloading the capsules in vertical irradiation holes of reactor pools. The instrumented capsule includes a capsule main body installed in the vertical irradiation hole. The capsule main body consists of a shell and several instruments, such as thermocouples, dosimeters, a vacuum control pipe, and heaters housed in the shell.

Abstract: A method of producing an isotope comprising directing electrons at a converting material coated with a coating material, the coating material having an atomic number of n, whereby interaction of the electrons with the converting material produces photons, and whereby the photons produced interact with the coating material to produce an isotope having an atomic number of n−1. In preferred embodiments, the converting material is Tungsten, the coating material having an atomic number of n is Radium-226, and the isotope having an atomic number of n−1 is Radium-225.

Abstract: An instrumented capsule for material irradiation tests in research reactors. The instrumented capsule performs an optimum material irradiation test under a testing environment similar to the operational environment of a real reactor. The capsule minimizes the influence of flow-induced vibration caused by forced-circulation-type coolant flow in a research reactor, and overcomes the problems experienced in the conventional breakable parts of instrumented capsules which may be broken during the process of loading/unloading the capsules in vertical irradiation holes of reactor pools. The instrumented capsule includes a capsule main body installed in the vertical irradiation hole. The capsule main body consists of a shell and several instruments, such as thermocouples, dosimeters, a vacuum control pipe, and heaters housed in the shell.

Abstract: A particle accelerator assembly with a liquid-target holding assembly usable to produce radioisotopes in liquid targets. A particle accelerator is configured to produce a particle beam along a beam axis, and the liquid-target holding assembly connected to the particle accelerator. The liquid-target retaining assembly has a mounting portion coupled to the particle accelerator, and the mounting portion is configured to receive the particle beam therethrough. A liquid-target holder is connected to the mounting portion and has a holder body with a target cavity that contains a liquid target therein. The target cavity has a longitudinal axis oriented at an acute angle relative to the particle beam axis. The target cavity has a first depth along an axis perpendicular to the longitudinal axis and has a projected depth along the beam axis greater than the first depth.

Abstract: A system and method for rapidly analyzing elemental abundances in rock or soil samples (14) under field conditions. The system uses a portable neutron source (12) to allow neutron activation analysis of elements having identifiable radioactive decay characteristics. A radiation detector (18) detects radiation released by the sample (14) and provides radiation testing results to an amplifier (26) for computing the concentration of trace elements in the sample with a high degree of accuracy.

Abstract: A thulium oxide-containing mixture consisting of a matrix material in which the thulium oxide is homogeneously distributed and forms therewith a body, which can be radioactivated by exposure to neutron radiation.

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.

Abstract: A method and apparatus for optimizing the production of Pu-238 in a nuclear reactor during normal reactor operation is disclosed wherein the production of Pu-238 is confined to one or more selectively replaced fuel cells with target cells located in the inside of the active volume of the reactor core to maximize the neutron flux for target irradiation. The target cells are modified existing nuclear fuel assembly cells having some fuel rods replaced with target rods of Np-237 forming a cluster array and having rings of water filled rods surrounding the target cluster to produce the desired optimal Pu-238 production.

Abstract: The invention describes a storage and dispatch container for variable quantities of radioactive miniature radiation sources as well as a locking and opening device for the said storage and dispatch container and is applicable for the transport of radioactive miniature radiation sources in well organized and undamaged condition. The dispatch containers serve as storage depots at the same time and meet the requirements of radiation safety with passive protection from loss. Their construction permits automatic filling or transfer of the contents using a corresponding device. The container is characterized in that a capillary tube (8) for the uptake of the radiation sources (15) is arranged in the main body (1) of the container and that the main body (1) exhibits a lower end-piece (2) with a fluid-medium connection (4) as well as an upper end-piece (3) with an input/output opening (3a) for the radiation sources (15), which can be locked by means of a locking mechanism (10).

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: The present invention provides a positron source essentially consisting of a carbon member having 18F bound onto the surface thereof, a method of preparing the same, and an automated system for supplying the same. In the present invention, the positron source is prepared by irradiating a solution containing both H218O and a small amount of natural fluorine ions with a beam of charged particles to generate 18F, and then passing an electric current through the solution using a carbon member 40 as an anode to cause to bind the generated 18F onto the surface of the carbon member.

Abstract: 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.

Abstract: A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith.

Abstract: Iodine-125 is produced by neutron irradiation of .sup.124 Xe gas to form .sup.125 Xe and permitting decay of .sup.125 Xe to form .sup.125 I. Irradiation of the xenon-124 is effected in a first chamber within an enclosure and decay is effected in a second chamber within the enclosure and free from neutron flux. The apparatus is submersible in a nuclear reactor pool so as to absorb any radiation escaping the apparatus during the process. Xenon can be caused to move between the chambers remotely, underwater. The second chamber is removable from said enclosure and is transported to a suitable location to recover the .sup.125 I from its interior. Such recovery is effected by admitting an aqueous wash solution into the second chamber, whereupon it is heated, causing water from the wash solution to reflux and cleanse the interior surfaces of the second chamber, thus creating an aqueous solution of .sup.125 I, which then is caused to drain into a suitable container.

Abstract: A device for carrying out a surveillance program to monitor the environmental effect of radiation and high-temperature oxygenated water on the shroud material in an operating reactor. The device is a holder containing shroud material specimens and encapsulated neutron flux monitors. The holder is installed on the shroud wall and left in place for a predetermined period of reactor operation time for the purpose of monitoring the neutron fluence effect on the shroud material specimens housed in the holder. The specimen holder is later removed from the reactor. The specimens are removed from the holder and examined in a laboratory to determine any changes in material properties. The specimen holder comprises a bolt-like device having a hollow head and a threaded shaft. The hollow head provides space for material specimens and neutron flux monitors. The specimen holder is attached to the shroud wall by screwing the threaded shaft into a threaded hole in shroud wall.

Abstract: An apparatus for carrying out a surveillance program to monitor the neutron fluence and its effect on vessel materials at a position in the annular space between the pressure vessel and core shroud of a boiling water reactor for the purpose of monitoring vessel embrittlement. The apparatus includes an offset capsule holder assembly which fits in an existing capsule holder attached to the inner surface of the pressure vessel wall. The offset capsule holder assembly positions a new capsule holder radially closer to the core, by an amount determined by neutron transport calculations. The new capsule holder is geometrically identical to the original, or a "replacement in kind", allowing the original surveillance capsules to be immediately reinstalled. With the water moderator in the downcomer annulus, the fluence rate increases significantly when the surveillance capsule is moved radially inward from the pressure vessel inside surface toward the core.

Abstract: A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith.

Abstract: This invention relates to a method and apparatus for the generation of isotopes, and in particular radioisotopes, from a target material which is not normally a solid and which, when bombarded by selected high energy particles, produces the selected isotope. A surface is provided which is preferably of a thermally-conductive material, which surface is cooled to a temperature below the freezing temperature of the target material. A thin layer of target material is then frozen on the surface and the target material is bombarded with the high energy particles. The beam of high energy particles is preferably at an angle to the surface such that the particles pass through a thickness of the target material greater than the thickness of the layer before reaching the surface. When the desired quantity of isotope has been produced from the target material, the target material, which has now been altered nuclearly to contain the selected isotope, is removed from the surface.

Abstract: An irradiator (4) is provided for irradiating lumps of ore to detect the presence of gold in the lumps by neutron activation analysis. The irradiator (4) consists of a close packed array of three inner cylindrical ducts (14) and three outer cylindrical ducts (12) through which the lumps of ore are passed, with three neutron sources (16) arranged in the spaces between the inner ducts (14) and the outer ducts (12) to irradiate the ducts (12, 14) and to activate any gold by the reaction .sup.197 Au (n, n'.gamma.) .sup.197 Au. Each inner duct (14) is thus adjacent to two neutron sources (16), and is or larger cross-sectional area than the outer ducts (12).

Abstract: A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm.sup.2 of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99.

Abstract: There are provided container vessels for the production and transportation of short-lived isotopes by irradiation from an accelerator, comprising a hermetically sealed container with a window in one of its walls which fits the exit window of such accelerator, and through which a suitable material contained in the said container vessel can be irradiated. There is also provided a method for the production of such short-lived positron sources for use in tomography, which comprises attaching a container vessel defined above adjacent to the exit window of an acceletator, irradiating a suitable material in said container, detaching the said container and working up the positron source in a radiochemistry laboratory.

Abstract: A system and process for the production of nitrogen-13 atoms from carbon-13/fluid slurry is provided. The system (10) includes a device (14) for producing a proton beam (15) which travels along a preselected path and strikes a target in slurry. This target is positioned in the path of the proton beam (15) such that subjection of the target to such beam produces nitrogen-13 atoms in a predetermined form. The nitrogen-13 atoms are conducted from the target area and carried to a purification device for collecting a purified product containing such atoms. The cooling system serves to dissipate heat generated during the production of such nitrogen-13 atoms.

Abstract: An irradiator for irradiating lumps of ore, to activate a selected substance in the ore by neutron activation, consists of a cylindrical chamber 10, a vibrated conical base 20 to control passage of the lumps through the chamber 10, and at least one coaxial annular neutron source 30 at one end of the chamber 10. The neutron source 30 is arranged so that all the lumps of ore are activated uniformly.

Abstract: A process for reliably and consistently producing astatine-211 in small controlled volumes of a solution, which is selected from a choice of solvents that are useful in selected radiopharmaceutical procedures in which the At-211 activities are to be applied.

Abstract: A method for simultaneously preparing Radon-211, Astatine-211, Xenon-125, Xenon-123, Iodine-125 and Iodine-123 in a process that includes irradiating a fertile metal material then using a one-step chemical procedure to collect a first mixture of about equal amounts of Radon-211 and Xenon-125, and a separate second mixture of about equal amounts of Iodine-123 and Astatine-211.

Abstract: A means for and method of producing and retaining tritium utilizing lithium bismuth and nickel is disclosed herein. The lithium bismuth serves to produce the tritium when exposed to neutrons. The nickel serves to dissolve and thereby retain the tritium which is produced by the lithium bismuth. As disclosed herein, both of these materials are contained within a common tubular housing which is pervious to the neutrons but impervious to any tritium which is produced therein.

Abstract: An apparatus for moving an object in an isolated environment may be employed as a high pressure and temperature facility for testing steam generator tubes. A tube to be tested extends through an opening in a plate that is mounted in a test vessel. The vessel is partially filled with water having selected contaminants, and heated water under high pressure is circulated through the tube to raise the temperature and pressure within the vessel. A lever arm having an inner end and an outer end extends through an opening in the test vessel. A vibration-coupler connects the inner end of the arm to the tube under test, and a fulcrum-former operationally connects an intermediate portion of the arm to the test vessel. The outer end of the lever arm is connected to a plug element which is shaken, so that the arm pivots about a fixed point at the fulcrum-former and the vibration-coupler moves the tube under test with respect to the plate.

Abstract: A heat pipe stablized specimen container for irradiation of specimens at substantially constant temperature within a liquid metal cooled fast reactor comprises a heat pipe containing a vaporizable substance such as sodium. The container is of double-walled construction with the gap filled with argon and at top of the container a volume of argon is trapped within a cavity of the liquid metal level within the container in such a way that retention of argon in this zone is not dependent on sealing welds in the structure of the container, the argon blanket in this zone affording thermal insulation at the top of the container and also around part of the heat pipe, viz an adiabatic section of the latter.

Abstract: A target arrangement for spallation-neutron-sources, according to which target material is continuously present at the point of incidence of a proton beam. The target material is arranged at the periphery of a rotary wheel which is internally cooled.

Abstract: The present invention relates to an upper neutron protection device for a nuclear reactor assembly.This device comprises at least one container partly filled with a neutron-absorbing product and maintained within a wall located in the upper part of the assembly by at least one spacing plate.Application to fast neutron reactors.

Abstract: A composition is described useful in the production of tritium in a nuclear eactor. Lithium aluminate particles are dispersed in a matrix of zirconium. Tritium produced by the reactor of neutrons with the lithium are absorbed by the zirconium, thereby decreasing gas pressure within capsules carrying the material.

Abstract: Apparatus for the transfer and positioning of targets in an irradiation installation equipped with an access lock of axis Z.sub.3 Z.sub.4 and within which there is a high vacuum, the installation being located in a protective enclosure defined by a shielded wall, including a telescopic assembly of axis X.sub.1 X.sub.2 located within the protective enclosure, the telescopic assembly having a free end able to carry the target to be positioned and being located on a support, and the support can be given a movement enabling it to move between a first target handling position in which the satisfactory operation of its components can be checked and a second position in which the X.sub.1 X.sub.2 axis of the telescopic assembly coincides with the Z.sub.3 Z.sub.4 axis of the access lock and the free end introduced into the lock.

Abstract: A method for the production of .sup.211 Rn comprising bombarding .sup.209 Bi with .sup.7 Li particles utilizing the nuclear reaction.sup.209 Bi(.sup.7 Li,5n).sup.211 Rn.The method provides a simple spectrum from which .sup.211 Rn can be easily isolated in a highly pure condition.