Abstract: Provided is a neutron beam transmission adjusting device including a neutron beam transmission unit including a neutron reactant and capable of modulating an energy and/or a flux of a neutron beam transmitted through the neutron beam transmission unit.

Abstract: An apparatus for supporting spent nuclear fuel. The apparatus may include a basket apparatus that is designed to be inserted into a cavity of a container or cask. The basket apparatus may be formed by arranging a plurality of slotted plates in an intersecting manner. The slotted plates may form fuel cells for storing fuel assemblies with spent nuclear fuel rods therein and flux trap spaces between adjacent ones of the fuel cells. Furthermore, the apparatus may include reinforcement members positioned in the flux traps to increase the structural strength of the basket apparatus.

Abstract: An apparatus for radiation shielding is provided. The apparatus includes a first housing element and a first plurality of magnetic elements arranged in a first array on the first housing element. The first array is configured to generate a first tapered magnetic field and, using the first tapered magnetic field, deflect incoming radiation away from a protected element.

Abstract: An exemplary sheetlike insulation material precursor and an exemplary insulation material are disclosed that can feature a particularly high thermal conductivity. The insulation material precursor can be characterized in that a layer of resin on each of two outer sides of a core laminate of interconnected polyester nonwovens and a polyester film is at the B-stage and has a weight fraction of at least 5% of boron nitride.

Abstract: An instrument for assaying radiation includes a radiation sensor and a collimator that covers at least a portion of the radiation sensor. The collimator defines a first field of view to the radiation sensor. An insert in the collimator defines a second field of view to the radiation sensor that is less than the first field of view.

Abstract: The preferred embodiments of the present invention are directed to methods and systems for dynamic route estimation and prediction using discrete sampled location updates from various mobile devices for the purpose of providing a graphical representation of a mobile device's route along a known network path of map data. The embodiments also provide supplemental route metrics, such as traveled distance, elapsed time, etc., and the capability to assign destination points for the purpose of providing the ability to modify location update points in an application, such as a route planner, and/or to store the dynamically generated route based on various preferences for later retrieval.

Abstract: A nuclear fusion reactor first wall component includes a copper alloy element, an intermediate metal layer made from niobium and a beryllium element, directly in contact with the intermediate metal layer. The intermediate niobium layer is further advantageously associated with a mechanical stress-reducing layer formed by a metal chosen from copper and nickel. This mechanical stress-reducing layer is in particular arranged between the intermediate niobium layer and the copper alloy element. Furthermore, when the mechanical stress-reducing layer is made from pure copper, a layer of pure nickel can be inserted between the niobium and the pure copper before diffusion welding. Such a component presents the advantage of having an improved thermal fatigue behavior while at the same time preventing the formation of intermetallic compounds at the junction between the beryllium and the copper alloy.

Abstract: The invention relates to the use of a mixture comprising erbium and praseodymium as a radiation attenuating composition, i.e. as a composition that can attenuate ionizing radiation, in particular X- and gamma-type electromagnetic radiation. The invention also relates to a radiation attenuating material comprising an erbium- and praseodymium-based composition, as well as a protective article which provides group or individual protection against ionizing radiation and comprises said material. The invention is suitable for use in nuclear medicine (scintigraphy, radiotherapy, etc.), radiology, medical imaging, the nuclear industry, etc.

Abstract: The invention relates to a neutron reflector block. The neutron reflector block comprises a first portion and a second portion. The first portion has a first end face and oppositely located intermediate shoulders which are spaced from the first end face. The first end face and the intermediate shoulders are bounded by spaced side faces and spaced upper and lower faces. The second portion protrudes from the first portion between the intermediate shoulders and has spaced side faces and spaced upper and lower faces. The second portion side faces are more narrowly spaced relative to the first portion side faces. The second portion also has a second end face located oppositely to the first end face.

Abstract: An overall lead-free X-ray shielding rubber compound material. The overall lead-free X-ray shielding rubber compound material uses rare earth mixture to replace lead, simultaneously adds metal tin and compounds thereof, metal tungsten and compounds thereof and bismuth and compounds thereof as shielding main materials and is further compounded with rubber to prepare the compound material which can realize the overall shielding and the complete lead-free property within the energy range of 40-170 kVp. When rare earth and bismuth materials are used, the way of combined use of two metal element inorganic compounds and unsaturated organic complexes is adopted, and the in-situ reaction and the compounding with a polymer matrix are carried out, thereby leading the shielding element disperse phase to form nano-micro-level dispersed particles.

Abstract: An energy filter allows, particularly at lower beam energies, a determined spread of the beam energies in order to preserve the beam edges and to spread the Bragg peak at each individual beam energy. The energy filter behaves similarly to a ridge filter and spreads out the Bragg peak of a low energy proton beam (70-100 MeV) so that energy modulation of the beam can be done with steps of 5 mm in one go over the full range of 235-70 MeV. Due to its mechanical flexibility, the energy filter can be placed on the skin of the patient which minimizes the effect of scattering in the filter due to the short distance behind a layer of a plurality of metal particles within a flexible soft plastic sheet to the skin of the patient.

Abstract: The present invention is directed to composite metal foams comprising hollow metallic spheres and a solid metal matrix. The composite metal foams show high strength, particularly in comparison to previous metal foams, while maintaining a favorable strength to density ratio. The composite metal foams can be prepared by various techniques, such as powder metallurgy and casting.

Abstract: Boron cage compound-containing materials for shielding and absorbing neutrons. The materials include BCC-containing composites and compounds. BCC-containing compounds comprise a host polymer and a BCC attached thereto. BCC-containing composites comprise a mixture of a polymer matrix and a BCC filler. The BCC-containing materials can be used to form numerous articles of manufacture for shielding and absorbing neutrons.

Abstract: A thermal neutron shield comprising boron shielding panels with a high percentage of the element Boron. The panel is least 46% Boron by weight which maximizes the effectiveness of the shielding against thermal neutrons. The accompanying method discloses the manufacture of boron shielding panels which includes enriching the pre-cursor mixture with varying grit sizes of Boron Carbide.

Abstract: An energy modulator for use with a particle source that provides a beam of particles includes a first block moveable between a first position and a second position, wherein when the first block is at the second position, it is in a path of the beam, and a second block moveable relative to the first block, wherein the second block and the first block are offset from each other in a direction of the beam, wherein the first block has a first energy absorption characteristic, and the second block has a second energy absorption characteristic that is different from the first energy absorption characteristic.

Abstract: To include a step of installing a hollow container (1) at a predetermined portion of an object to be shielded (100), a step of feeding fluid into the container (1) via a hose (22) by a fluid feeding unit (2), and a step of transporting and filling a granular shielding material into the container (1) via the hose (22) by supplying the shielding material to the fluid by a shielding-material supply unit (3). With this arrangement, because a shielding material is fed into the container (1) together with the fluid and filled therein at a remote place from the object to be shielded (100), a worker does not need to approach the object to be shielded (100). Further, because a shielding effect is improved by the granular shielding material, an amount of radiation to the worker can be reduced easily and sufficiently.

Abstract: Masses for obtaining poured concrete, concrete for bricks, concrete for tiles or mortar are known, in which Portland cement and Colemanite, water and additives to regulate the process are involved as aggregate. The invention achieves a remarkable increase in the capacity of neutron radiation protection of the material. For this, Portland cement is replaced by Alumina cement and a new component is inserted into the mass, specifically anhydrous calcium sulfate, the Colemanite staying as aggregate.

Abstract: In one embodiment, a system for aligning collimators in an imaging system includes a transmitter coupled to a first detector and configured to transmit a beam, and a receiver coupled to a second detector and configured to receive the beam transmitted from the first detector. The alignment system also includes a cart comprising an alignment device with the cart configured to hold at least two collimators. The system includes a control system configured to align the first and second detectors with the at least two collimators using the alignment device.

Abstract: A thermal neutron shield comprising concrete with a high percentage of the element Boron. The concrete is least 54% Boron by weight which maximizes the effectiveness of the shielding against thermal neutrons. The accompanying method discloses the manufacture of Boron loaded concrete which includes enriching the concrete mixture with varying grit sizes of Boron Carbide.

Abstract: Irradiation device for proton and/or ion beam therapy, said device comprising a radiation source, a beam guiding device, and a therapy room comprising a treatment site and an access, wherein the therapy room is arranged in a first plane, and the treatment beam is directed into the therapy room from a second plane above or below the first plane, and oriented towards the treatment site so that the treatment beam is directed away from the access. In the therapy room, a shielding is provided, which is open towards the treatment site and associated with the entrance region of the treatment beam into the therapy room so that the access is arranged on the side of the shielding opposing the treatment site, and a labyrinth leading from the access to the treatment site is provided laterally offset to the treatment beam proceeding in the therapy room and to the shielding.

Abstract: A flexible, lightweight radiation absorbing sheet or shield includes heavy metal particles in one layer and mid-atomic number particles in another layer, the layer that will be adjacent to the patient. The shield is particularly intended for protection of the wearer and others from radiation emanating from a therapeutic source positioned within the patient's body. With the disclosed multi-layer shield construction, backscattered radiation off the heavy metal particle layer, affecting the patient's adjacent tissue, is minimized.

Abstract: A shield for absorbing radiation emitted during generation of a radioisotope. The shield includes an inner portion fabricated from a first type of shielding material. The shield also includes an outer portion fabricated from a second type of shielding material wherein the outer portion serves as a mold for forming the inner portion. The inner portion may be fabricated from a material which shields against gamma rays such as concrete. The outer portion may be fabricated from a material which moderates neutrons such as high density polyethylene. Additional shielding materials may be embedded into the inner portion as desired.

Abstract: A shield for absorbing radiation emitted during generation of a radioisotope. The shield includes an inner portion fabricated from a first type of shielding material. The shield also includes an outer portion fabricated from a second type of shielding material wherein the outer portion serves as a mold for forming the inner portion. The inner portion may be fabricated from a material which shields against gamma rays such as concrete. The outer portion may be fabricated from a material which moderates neutrons such as high density polyethylene. Additional shielding materials may be embedded into the inner portion as desired.

Abstract: A conduction cooled neutron absorber may include a metal matrix composite that comprises a metal having a thermal neutron cross-section of at least about 50 barns and a metal having a thermal conductivity of at least about 1 W/cm·K. Apparatus for providing a neutron flux having a high fast-to-thermal neutron ratio may include a source of neutrons that produces fast neutrons and thermal neutrons. A neutron absorber positioned adjacent the neutron source absorbs at least some of the thermal neutrons so that a region adjacent the neutron absorber has a fast-to-thermal neutron ratio of at least about 15. A coolant in thermal contact with the neutron absorber removes heat from the neutron absorber.

Abstract: A neutron absorbing insert for use in a fuel rack and method of manufacturing the same. In ones aspect, the invention is a neutron absorbing apparatus for insertion into a fuel rack comprising: a sleeve having a first wall and a second wall, the first and second walls forming a chevron shape; and the first and second wall being a single panel of a metal matrix composite having neutron absorbing particulate reinforcement bent into the chevron shape along a crease.

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: Boron cage compound-containing materials for shielding and absorbing neutrons. The materials include BCC-containing composites and compounds. BCC-containing compounds comprise a host polymer and a BCC attached thereto. BCC-containing composites comprise a mixture of a polymer matrix and a BCC filler. The BCC-containing materials can be used to form numerous articles of manufacture for shielding and absorbing neutrons.

Abstract: A radiation therapy system for heavy ions employs a rocking motion of a fan beam used to treat the patient, the fan beam having individually modulated beamlets, the rocking limited in angular extent to provide improved conformance of the dose to a tumor while shielding distal tissue from radiation.

Abstract: A shield for a well logging instrument includes an outer layer including a reinforcing fiber disposed in a matrix and an inner layer including a thermal neutron absorbing material disposed in a matrix. The thermal neutron absorbing material is selected to emit capture gamma rays having energy outside a selected energy range.

Abstract: The present invention provides devices and methods that protect against exposure to remote sources of electromagnetic radiation (EMR). As such, the devices provide protection against a plurality of electrical equipment used in ordinary households and employment settings. The device includes a housing, a solenoid operably connected to a driver and a polymer. The solenoid generates incident radiation which results in the polymer emitting electromagnetic oscillations at frequencies that counter adverse effects associated with the subject's exposure to the electromagnetic radiation.

Abstract: Disclosed are radiation shields substantially enclosing a source of polyenergetic positive ions. The shielding layers are spatially arranged to absorb substantially all unwanted radiation arising directly or indirectly from the polyenergetic positive Also disclosed are methods of shielding unwanted radiation leaking from a system providing a therapeutic dose of polyenergetic positive radiation, as well as shielded polyenergetic positive ion selection systems.

Abstract: A compressed powder composite (CPC) material for absorbing neutrons emitted from spent nuclear fuel thereby preventing the initiation of a chain reaction. The CPC material is typically provided as a substantially insoluble cylindrical pellet that is highly resistant to corrosion and is not subject to the failure modes associated with the alloy materials typically used in neutron absorption materials. The pellet preferably includes a dendritic nickel powder substantially uniformly mixed with a neutron absorber powder material, preferably boron carbide. Tubes filled with CPC materials, such tubes for replacing control roads so that a spent nuclear fuel assembly may be disposed of substantially indefinitely.

Abstract: A transport/storage cask for a radioactive material has an inner shell, an outer shell and a circular gamma ray shielding layer and a circular neutron shielding layer both of which are placed between the inner shell and the outer shell. The gamma ray shielding layer is formed by aligning a plurality of gamma ray shielding blocks composed of lead in a block shape in the circumferential direction. The entire gamma ray shielding block in the axial direction is covered with a copper tube having a higher elasticity limit than the gamma ray shielding block. In the above transport/storage cask, the gamma ray shielding layer composed of lead or a lead alloy is not easily deformed.

Abstract: Laminated lead-free radiation protection material (10, 12, 14) comprising at least two individual composite layers (2), each individual composite layer (2) comprising a secondary radiation layer (4) with a low Z material and a barrier layer (4) with a high Z material, wherein the individual composite layers (2) are arranged in the radiation protection material (10, 12, 14) in such a way that a barrier layer (8) is arranged on both surfaces (18, 20) of the radiation protection material (10, 12, 14), and the respective secondary radiation layer (8) is arranged at a distance from the surface (18, 20).

Abstract: A radiation shielding system includes at a first shielding member and at least a second shielding member that is coupled to the first shielding member. Each of the first and second shielding member includes a moderator material. At least the first shielding member includes at least one locking member extending from a surface of a region where the at least one locking member is disposed. At least the second shielding member includes at least one recessed area on a side of the second shielding member corresponding to the side of the first shielding member. The second shielding member is coupled to the first shielding member by the recessed area receiving the locking member.

Abstract: A radiation protection shield for protecting medical personnel from radiation being applied to a patient positioned on a table. The shield includes a frame and a primary screen including a radiation-resistant material connected to said frame.

Abstract: The invention relates to a multi-layered radiation protection wall for shielding against gamma and/or particle radiation of a reaction site of an accelerator facility, wherein the radiation protection wall comprises a sandwich-like structure with at least a first and a second layer arrangement, wherein the first layer arrangement has at least a primary shielding layer and the second layer arrangement has at least a secondary shielding layer. Thereby, at least one of the first and the second layer arrangements is sub-divided into a plurality of wall segments, whereby a selective disposal is made possible. Thus an increased cost efficiency is achieved and the environmental impact is lowered.

Abstract: A neutron chopper according to the present invention includes a housing which internally forms a sealed space, the housing having window portions through which neutrons pass, a fixed shaft which is fixed inside the housing, a rotor which is rotatably supported by the fixed shaft, the rotor provided with a blocking portion which can block neutrons passing through the housing, and a motor which is provided inside the housing for rotating the rotor of the neutron chopper, where a stator of the motor is fixed to the fixed shaft, and a rotor of the motor receives a rotating force from the stator around the fixed shaft, and is fixed to the rotor of the neutron chopper. The neutron chopper is formed with small size, and neutron guides are easily disposed closely, consequently vacuum leak is hardly occurred in the neutron chopper.

Abstract: There is provided a neutron shielding material which has heat resistance and has ensured neutron shielding performance even in a high-temperature environment during storage of a spent nuclear fuel for high burnup. A neutron shielding material having improved heat resistance and ensured neutron shielding performance due to the absence of an amine curing agent is provided by a neutron shielding material composition comprising a polymerization initiator, a polymerization component, a density increasing agent and a boron compound. As the polymerization component of the present invention, an epoxy component and an oxetane component are particularly preferably used.

Abstract: A neutron shield material that exhibits high heat resistance and ensures neutron shielding capacity. A composition for neutron shield material excelling in heat resistance and ensuring neutron shielding capacity is provided by comprising a hydrogenated bisphenol type epoxy of the formula: (1) (wherein each of R1 to R4 is independently selected from the group consisting of CH3, H, F, Cl and Br, and n=0 to 2), a hardening agent component having at least one cyclic structure and two or more amino groups, a density increasing agent and a boron compound.

Abstract: The invention is a composite radiation absorber constructed from multiple layers of a rubber or rubber like matrix material filled containing a radiation absorptive element, or a plurality of radiation absorptive elements, that differ from layer to layer. The invention also teaches that mixtures of radiation absorbing elements within layers may improve overall radiation absorption performance. This multiple absorption approach offers significant advantages to users in the shielding of undesirable ionizing or acoustic radiation fields. This invention differs significantly from prior art in that heterogeneous mixtures of differing absorbers and multiple (more than two) layers of material are used and found to be advantageous in the control of penetrating radiation fields. This invention also differs from prior art in that some mixed or layered absorptive components also contribute significantly to the absorber utility as in the case of surface magnetic additives.

Abstract: The present invention relates to a well type neutron counter containing a He-3 detector which includes at least one annular gas layer in a polyethylene moderator, which includes a body formed of a neutron moderator and having a sample cavity for inserting a sample of nuclear material therein; and an annular He-3 detector tube including at least one annular gas layer into which at least He-4 or He-3 gas or their mixture is injected and a plurality of anode rods stood in the annular gas layer with an equal spaces, wherein the He-3 detector tube is formed in an inside of the body so as to surround the sample cavity. The neutron counter has a largely reduced size, simplified structure and resultant decreased failure rate as compared to a conventional counter with a large volume.

Abstract: A method, device and retrofitting kit is disclosed that will protect materials that are housed within a storage device from one or more forms of radiographic imaging. A target subject is at least partially covered with a first and second layer of radiographic cloaking material. The first layer of radiographic cloaking material is configured to defeat a first type of radiographic beam, such as a photon beam. The second layer of radiographic cloaking material is configured to defeat a second type of radiographic beam, such as a particle beam.

Abstract: The invention relates to a glove box with a sealed containment delimited at least partially by a wall having a polycarbonate partition (6) and a biological protection partition (8) spaced from the polycarbonate partition and arranged externally with respect to same, the glove box also comprising lighting means of the containment, said lighting means comprising a light source (20). According to the invention, the light source (20) is housed between the polycarbonate partition (6) and the biological protection partition (8).

Abstract: A neutron moderator includes a neutron generator; a neutron moderating material arranged on one side of the neutron generator; a gamma ray shielding material covering an external surface of the neutron moderating material; and a thermal neutron absorbing material covering the external surface of the neutron moderating material except a side where the neutron generator is arranged.

Abstract: A conduction cooled neutron absorber may include a metal matrix composite that comprises a metal having a thermal neutron cross-section of at least about 50 barns and a metal having a thermal conductivity of at least about 1 W/cm·K. Apparatus for providing a neutron flux having a high fast-to-thermal neutron ratio may include a source of neutrons that produces fast neutrons and thermal neutrons. A neutron absorber positioned adjacent the neutron source absorbs at least some of the thermal neutrons so that a region adjacent the neutron absorber has a fast-to-thermal neutron ratio of at least about 15. A coolant in thermal contact with the neutron absorber removes heat from the neutron absorber.

Abstract: A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360° and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Abstract: A downhole tool for performing measurement of a formation. The tool comprising a housing surrounding a source for generating neutrons and a detector for detecting the neutrons. A shield is located outside of, or embedded in, the housing and focuses the neutrons.

Abstract: A method, device and retrofitting kit is disclosed that will protect materials that are housed within a storage device from one or more forms of radiographic imaging. A target subject is at least partially covered with a first and second layer of radiographic cloaking material. The first layer of radiographic cloaking material is configured to defeat a first type of radiographic beam, such as a photon beam. The second layer of radiographic cloaking material is configured to defeat a second type of radiographic beam, such as a particle beam.

Abstract: The invention concerns a neutron shielding material for maintaining sub-criticality based on unsaturated polymer: Said material comprises an unsaturated polyester resin, at least an inorganic boron compound, and at least a hydrogenated inorganic compound, in amounts such that the boron concentration is 4.1021 to 25.1021 atoms per cm3 and the hydrogen concentration is 3.1022 to 5.5.1022 atoms per cm3.