Abstract: The invention comprises a method and apparatus for reducing a kinetic energy of positively charged particles, comprising the steps of: (1) transporting the positively charged particles from an accelerator into an exit nozzle system along a beam line; (2) providing a first chamber of the exit nozzle system, the first chamber comprising: an incident side comprising an incident aperture, an exit side comprising an exit aperture, and a beam path of the positively charged particles from the incident aperture to the exit aperture; (3) filling the beam path in the chamber with a liquid; and (4) using the liquid to reduce the kinetic energy of the positively charged particles. The kinetic energy dissipater is optionally used in combination with a proton therapy cancer treatment system and/or a proton tomography imaging system.

Abstract: In order to improve flux and quality of neutron sources, the disclosure provides a beam shaping assembly for neutron capture therapy includes: a beam inlet; a target, wherein the target has nuclear reaction with an incident proton beam from the beam inlet to produce neutrons; a moderator adjoining to the target, wherein the neutrons are moderated by the moderator to epithermal neutron energies, the moderator includes a main body and a supplement section surrounding the main body, the main body and the supplement section form at least a tapered structure; a reflector surrounding the moderator; a thermal neutron absorber adjoining to the moderator; a radiation shield arranged inside the beam shaping assembly, wherein the radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation; and a beam outlet.

Abstract: A chemical detection system includes a frame, an emitter coupled to the frame, and a detector coupled to the frame proximate the emitter. The system also includes a shielding system coupled to the frame and positioned at least partially between the emitter and the detector, wherein the frame positions a sensing surface of the detector in a direction substantially parallel to a plane extending along a front portion of the frame. A method of analyzing composition of a suspect object includes directing neutrons at the object, detecting gamma rays emitted from the object, and communicating spectrometer information regarding the gamma rays. The method also includes presenting a GUI to a user with a dynamic status of an ongoing neutron spectroscopy process. The dynamic status includes a present confidence for a plurality of compounds being present in the suspect object responsive to changes in the spectrometer information during the ongoing process.

Abstract: The present invention relates to a charged particle beam generator comprising multiple charged particle beam generator units. In particular, the present invention is concerned with apparatus for generating a high-energy, high-current proton beam such as are used in accelerator driven subcritical reactors. The present invention provides a method of generating a composite proton beam using a proton beam generator comprising multiple proton beam generator units. A negative hydrogen ion source is used to generate a beam of negative hydrogen ions in each unit. The negative hydrogen ions are stripped to create a proton beam in each unit, that is accelerated beam and guided to a common point where the beams are merged to form the composite proton beam.

Abstract: Provided is a modified target assembly in which the target fluid is moved within the target assembly in a manner that increases the effective density of the target fluid within the beam path, thereby increasing beam yield utilizing forced convection. The target may also include optional structures, such as nozzles, diverters and deflectors for guiding and/or accelerating the flow of the target fluid. The target assembly directs the target fluid along an inner sleeve in a direction opposite the direction of the beam current to produce a counter current flow and may also direct the flow of the target fluid away from the inner surface of the inner sleeve and toward a central region in the target cavity. This countercurrent flow suppresses natural convection that tends to reduce the density of the target fluid in the beam path and tends to increase the heat transfer from the target.

Abstract: In a shielded chamber for neutron therapy including a therapy room which has a central beam axis along which a high-energy therapy beam is introduced into the Chamber through one end wall thereof and which includes at the opposite end a labyrinth entrance with at least two shielding wall sections displaced longitudinally along the central beam axis and extending into the room from opposite side walls, the wall sections include structures for causing spallation to thereby generate from the high energy neutrons in the high energy neutron beam a plurality of low energy neutrons which are then moderated by the wall sections.

Abstract: A system is provided for generating high-energy particles and for inducing nuclear reactions. The system includes a laser and for emitting a laser beam, an irradiation target for receiving the laser beam and producing high-energy particles, and a secondary target for receiving the high-energy particles, thereby inducing a nuclear reaction. A method is also provided including producing a laser beam of high-intensity with an ultra-short pulse duration, irradiating the laser beam onto an irradiation target in order to ionize the irradiation target and produce a collimated beam of high-energy particles, and colliding the collimated beam of high-energy particles onto a secondary target containing a nuclei, thereby inducing a nuclear reaction on the secondary target.

Abstract: A method for transmuting spent fuel from a nuclear reactor includes the step of separating the waste into components including a driver fuel component and a transmutation fuel component. The driver fuel, which includes fissile materials such as Plutonium239, is used to initiate a critical, fission reaction in a reactor. The transmutation fuel, which includes non-fissile transuranic isotopes, is transmuted by thermal neutrons generated during fission of the driver fuel. The system is designed to promote fission of the driver fuel and reduce neutron capture by the driver fuel. Reacted driver fuel is separated into transuranics and fission products using a dry cleanup process and the resulting transuranics are mixed with transmutation fuel and re-introduced into the reactor. Transmutation fuel from the reactor is introduced into a second reactor for further transmutation by neutrons generated using a proton beam and spallation target.

Abstract: Method for analyzing a primary neutron beam of a neutron source, a neutron source having a beam monitor, and a beam monitor. Fission chambers which are arranged in the primary neutron beam are known as beam monitors. Fission processes initiated by the neutrons produce in the fission chambers free charge carriers which, given an applied electric voltage, effect an ionization current pulse by means of which the neutron is counted. Produced as by-product during fission are undesired fast neutrons and high-energy gamma radiation. In addition, the flux of slow neutrons can be substantially attenuated by the gas filling of the fission chambers. These disadvantages can be avoided in the case of the novel method, the novel neutron source and the novel beam monitor. Neutrons are scattered incoherently out of the primary neutron beam (1) by means of a scattering foil (4). A portion of the scattered neutrons (5) strike a detector device (6) which is arranged outside the primary neutron beam (1).

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: 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 subcritical reactor-like apparatus for treating nuclear wastes, the apparatus comprising a vessel having a shell and an internal volume, the internal volume housing graphite. The apparatus having means for introducing a fluid medium comprising molten salts and plutonium and minor actinide waste and/or fission products. The apparatus also having means for introducing neutrons into the internal volume wherein absorption of the neutrons after thermalization forms a processed fluid medium through fission chain events averaging approximately 10 fission events to approximately 100 fission events. The apparatus having additional means for removing the processed fluid medium from the internal volume. The processed fluid medium typically has no usefulness for production of nuclear weapons.

Abstract: A beam of accelerated charged particles irradiates an arsenide target, such as gallium arsenide or aluminum arsenide, to produce radioisotopes of selenium and other radionuclides. The irradiated target is placed in a niobium, tantalum, or graphite vessel and inserted into a tube. Metallic reagents consisting of an alloy of iron, nickel, and chromium (stainless steel) or metallic aluminum are mixed with the target material. The target is then heated to 1000-1100.degree. C. The metallic reagents prevent arsenic sublimation, destroy the crystalline structure of arsenide target, and remove other impurities, such as zinc-65. The target is then heated a second time to about 1300.degree. C. causing the selenium-72 to sublime and be deposited on a cooler wall of the tube or on a catcher foil surface. The deposited selenium-72 is recovered from the tube or foil.

Abstract: Improved efficiency process for preparing or breeding tritium gas from dense molten lithium alloy by bombardment of the alloy as a target material using a linear accelerator emitting a high energy proton beam to generate a neutron flux. The invention involves using a dense eutectic molten lead lithium alloy as the target material, directing the impact area within the body of molten target material, such as to a depth of about 2 meters of the target material, and continuously circulating the molten alloy past the impact area to dissipate the heat of reaction to provide a substantial lead source for maximum neutron production and to provide an effective lithium source to absorb the neutrons, to produce the highest possible amount of tritium per proton applied by the high energy proton beam. The formed tritium gas is insoluble in and separates from the molten alloy.

Abstract: Plutonium is effectively and economically rendered unsuitable for employment in a device for creating a nuclear detonation. Weapons-grade plutonium is made into ceramic fuel in the form of spheroids of submillimeter size, coated with multi-layer fission-product-retentive coatings and disposed in sealed fuel chambers in graphite block fuel elements. These elements are used to form a core for a modular helium-cooled high temperature nuclear reactor which is operated to efficiently generate power by causing the hot high pressure helium coolant to drive a gas turbine directly connected to an electrical generator, which nuclear fuel core has about a 3-year lifetime. Spent nuclear fuel elements are removed at the end of 3 years and shifted to form the core for an accelerator-driven helium-cooled reactor wherein a subcritical core of spent fuel elements is safely caused to effectively continuously fission by a neutron flux created by a Linac which bombards a lead target with a beam of high energy protons.

Abstract: A process for preparation of silicon-32 is provide and includes contacting an irradiated potassium chloride target, including spallation products from a prior irradiation, with sufficient water, hydrochloric acid or potassium hydroxide to form a solution, filtering the solution, adjusting pH of the solution to from about 5.5 to about 7.5, admixing sufficient molybdate-reagent to the solution to adjust the pH of the solution to about 1.

Abstract: A method of producing Al-26 from potassium chloride by exposing it to a proton beam in order to break potassium and chlorine atoms into smaller pieces, which include Al-26. The Al-26 is isolated from the potassium chloride and other substances produced by the beam by means of extraction and ion exchange.

Abstract: A system for extracting sodium, particularly radioactive .sup.22 Na, from aluminum utilizes a monel exhaust system for exhausting sodium vapor emitted from a molten aluminum target, in a draft of helium gas. The aluminum target is heated until it is melted in a graphite support cup. The graphite support does not react with the sodium. Moreover, the graphite is understood to be permeable to the helium gas, its porosity being believed to provide the significant advantage that the graphite holder will not absorb much of the sodium vapor. The use of graphite avoids a disadvantageous monel-aluminum reaction whereby an alloy from which sodium cannot be distilled is formed. The resulting sodium vapor is precipitated in a monel exhaust tube which is subjected to temperature control. Sodium can be rinsed from the monel exhaust tube with water.

Abstract: Charged-particles in the 45-15 MeV energy range incident upon isotopically enriched xenon-124 gas in a gas-target assembly cause nuclear reactions which yield radioactive xenon-123. The xenon-123, decaying either in the target assembly or in a decay vessel removed from the target assembly, yields iodine-123 with very low levels of radioactive contaminants.

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: A method of producing carrier-free .sup.67 Cu by proton spallation combined with subsequent chemical separation and purification is disclosed. A target consisting essentially of pressed zinc oxide is irradiated with a high energy, high current proton beam to produce a variety of spallogenic nuclides, including .sup.67 Cu and other copper isotopes. The irradiated target is dissolved in a concentrated acid solution to which a palladium salt is added. In accordance with the preferred method, the spallogenic copper is twice coprecipitated with palladium, once with metallic zinc as the precipitating agent and once with hydrogen sulfide as the precipitating agent. The palladium/copper precipitate is then dissolved in an acid solution and the copper is separated from the palladium by liquid chromatography on an anion exchange resin.

Abstract: A target arrangement for spallation-neutron-sources, according to which tet 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: A device for producing fissile material inside of fabricated nuclear elements so that they can be used to produce power in nuclear power reactors. Fuel elements, for example, of a LWR are placed in pressure tubes in a vessel surrounding a liquid lead-bismuth flowing columnar target. A linear-accelerator proton beam enters the side of the vessel and impinges on the dispersed liquid lead-bismuth columns and produces neutrons which radiate through the surrounding pressure tube assembly or blanket containing the nuclear fuel elements. These neutrons are absorbed by the natural fertile uranium-238 elements and are transformed to fissile plutonium-239. The fertile fuel is thus enriched in fissile material to a concentration whereby they can be used in power reactors. After use in the power reactors, dispensed depleted fuel elements can be reinserted into the pressure tubes surrounding the target and the nuclear fuel regenerated for further burning in the power reactor.

Abstract: An apparatus for precisely positioning materials test specimens within the optimum neutron flux path emerging from a neutron source located in a housing. The test specimens are retained in a holder mounted on the free end of a support pivotably mounted and suspended from a movable base plate. The support is gravity biased to urge the holder in a direction longitudinally of the flux path against the housing. Means are provided for moving the base plate in two directions to effect movement of the holder in two mutually perpendicular directions normal to the axis of the flux path.