Abstract: Radionuclides are produced with a pulsed neutron flux from a multiple repetition rate staged Z-pinch machine, the pulsed neutron flux is moderated, an activatable radionuclide precursor is exposed to the moderated pulsed neutron flux, and a corresponding radionuclide from the activatable radionuclide precursor is produced. High current pulses are passed through a target plasma of fusible material enclosed in a cylindrical liner plasma composed of a high-Z plasma to generate a magnetic field that compresses the liner plasma, and generates shock waves. The shock implodes the target plasma. The shock front propagates between an outer shock front and an axis of the target plasma so it is heated through shock dissipation and by adiabatic compression due to an imploding shock front produced in the outer liner plasma to fuse light nuclei and generate alpha particles and neutrons. Alpha particles trapped within the magnetic field further heat the target plasma.

Abstract: Disclosed herein are embodiments of systems and methods for creating radioisotopes. In one aspect, a Compact Fusion Neutron Source (CFNS) as described herein, can be used to create radioisotopes. The generation of the radioisotopes can utilize (n,2n), (n,p), (n,d), or (n,?) reactions, which can be caused by the high energy neutrons created by fusion. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: Example embodiments are directed to methods and apparatuses for generating desired isotopes within water rods of nuclear fuel assemblies. Example methods may include selecting a desired irradiation target based on the target's properties, loading the target into a target rod based on irradiation target and fuel assembly properties, exposing the target rod to neutron flux, and/or harvesting isotopes produced from the irradiation target from the target rod. Example embodiment target rods may house one or more irradiation targets of varying types and phases. Example embodiment securing devices include a ledge collar and/or bushing that support target rods within a water rod and permit moderator/coolant flow through the water rod. Other example embodiment securing devices include one or more washers with one or more apertures drilled therein to hold one or more example embodiment target rods in a water rod while permitting coolant/moderator to flow through the water rod.

Abstract: A material is exposed to a neutron flux by distributing it in a neutron-diffusing medium surrounding a neutron source. The diffusing medium is transparent to neutrons and so arranged that neutron scattering substantially enhances the neutron flux to which the material is exposed. Such enhanced neutron exposure may be used to produce useful radio-isotopes, in particular for medical applications, from the transmutation of readily-available isotopes included in the exposed material. It may also be used to efficiently transmute long-lived radioactive wastes, such as those recovered from spent nuclear fuel. The use of heavy elements, such as lead and/or bismuth, as the diffusing medium is particularly of interest, since it results in a slowly decreasing scan through the neutron energy spectrum, thereby permitting very efficient resonant neutron captures in the exposed material.

Abstract: A radioisotope is produced through any of the following reactions using a target material: (1) (n, 2n) reaction: two-neutron pickup reaction induced by neutrons, (2) (n, 3n) reaction: three-neutron pickup reaction induced by neutrons, (3) (n, n?) reaction: neutron inelastic scattering reaction, (4) (n, p) reaction: one proton-pickup reaction induced by neutrons, (5) (n, np) reaction: one neutron- and one proton-pickup reaction induced by neutrons, (6) (n, 4He) reaction: one 4He-pickup reaction induced by neutrons.

Abstract: A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

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 of isolating 186Re according to example embodiments may include vaporizing a source compound containing 185Re and 186Re. The vaporized source compound may be ionized to form negatively-charged molecules containing 185Re and 186Re. The negatively-charged molecules may be separated to isolate the negatively-charged molecules containing 186Re. The isolated negatively-charged molecules containing 186Re may be collected with a positively-charged collector. Accordingly, the isolated 186Re may be used to produce therapeutic and/or diagnostic radiopharmaceuticals having higher specific activity.

Abstract: A method and apparatus for reducing the radioactivity of a particle is disclosed. The method comprises the steps of: accelerating one or more first particle(s) comprising one or more neutron(s), proton(s) and electron(s) to a first velocity; colliding the accelerated particles(s) with one or more second particles in a collision zone located within a housing causing the first particle(s) and second particle(s) to form one or more collision mass(es) comprising alpha particles and electrons or/and protons and electrons, and in which substantially all neutrons of the first or second particles are converted into alpha particles or/and protons and electrons as a result of the collision; controlling the position of the collision mass(es) with electric or/and magnetic fields; and exhausting the collision mass from the housing wherein the collision mass comprises substantially only alpha particles or/and protons and electrons.

Abstract: Neutron bundles are formed as a result of interactions between polarized atomic core neutrons and anti-polar neutrons injected into atomic cores. Neutron bundles are groups of neutrons that can be produced and used in a process for making elements and isotopes, and also used in a process for the production of nuclear binding energy as the ultimate clean fuel for energy with an unlimited supply. Elements and isotopes are formed upon the introduction of protons onto neutron bundles. Nuclear fusion energy is produced when neutron bundles are made to react with each other in equipment designed for this purpose that includes a neutron bundle nuclear chain reactor.

Abstract: A variable-ratio neutron-gamma ray source comprises a neutron generator, a shield, a collimator, and an external gamma target. The neutron generator generates neutrons and the shield reduces external radiation exposure. The collimator collimates the neutrons into a neutron beam that traverses the shield. The external gamma target generates a dual neutron-gamma ray beam from the neutron beam, wherein the dual neutron-gamma ray beam has a variable neutron-gamma ratio as a function of a thickness of the external gamma target.

Abstract: A dual neutron-gamma ray source comprises a compact neutron generator, a shield, a collimator, and an internal gamma target. The shield surrounds the compact neutron generator. The collimator traverses the shield from the compact neutron generator to a collimator port. The internal gamma target is positioned within the collimator to generate gamma rays from the neutrons.

Abstract: A remote sensing device for detecting materials of varying atomic numbers and systems and methods relating thereto. A system for identifying a material includes a photon beam flux monitor for resolving a high-energy beam. A method for identifying a material includes casting an incident photon beam on the material and detecting an emerging photon beam with an array of fission-fragment detectors, a first set of scintillator paddles, and a second set of scintillator paddles.

Abstract: A method for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons. A method for producing antiprotonic x-ray cascade spectra.

Abstract: The patent specification and claims disclose a neutron flux source supplying both monoenergentic neutrons and a spectrum of neutron energies similar to the neutron emission of 252Cf. The neutron flux source is applied to interrogate unknown materials in closed containers for classification of the contents.

Abstract: Illustrative embodiments provide modular nuclear fission deflagration wave reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, modular nuclear fission deflagration wave reactors, modular nuclear fission deflagration wave reactor modules, methods of operating a modular nuclear fission deflagration wave reactor, and the like.

Abstract: A polarized neutron guide for separating neutrons into polarized neutrons while minimizing loss of the neutrons is provided. The polarized neutron guide includes a body, the first space and the second space, and a neutron separation space. The body includes super mirrors coated with a neutron-reflective thin film and the first and second spaces are formed by the first plate inside the body. The neutron separation space is formed by the second plate disposed at the entry of the first space and the third plate disposed at the entry of the second space. Spin-up polarized neutrons and spin-down polarized neutrons are simultaneously separated and transferred in the first and second spaces, respectively. Therefore, with minimum loss of the neutrons, the spin-up polarized neutrons and the spin-down polarized neutrons are effectively separated and collected.

Abstract: A method for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons.

Abstract: The system and method provide security and cargo handling personnel a versatile tool to rapidly check cargo for hidden radiological materials, explosives, drugs, and chemical weapons material. Gamma ray emission is stimulated by a pulsed neutron source. The gamma ray signature is used to classify the material. Passive gamma ray analysis can be used to detect and identify radiological material. The method of determining the contents of a target includes irradiating a target; detecting at least one spectrum emitted from the target; performing a primary analysis to extract a first set of indicators; and performing a secondary analysis to decide the contents of the target. The primary analysis utilizes either a least squares analysis or principal component analysis. The secondary analysis utilizes a generalized likelihood ratio test or support vector machines.

Abstract: The burnout of a fuel element in a reactor is determined by first transferring a fuel element from a reactor to a measuring position and then subjecting the transferred fuel element at the position to a neutron flux. A first detector measures the total ? radiation emitted by the transferred fuel element and thereafter, if the radiation measured by the first detector exceeds a predetermined first limit, the transferred fuel element is returned back to the reactor. If not, a second detector measures a magnitude of high energy ? radiation above 1 MeV emitted by the transferred fuel element and thereafter only if the radiation measured by the second detector exceeds a predetermined second limit, the transferred fuel element is transferred back to the reactor. The element is not returned to the reactor if the radiation measured by the second detector is below the second limit.

Abstract: A method and associated apparatus for detecting concealed fissile, fissionable or special nuclear material in an article, such as a shipping container, is provided. The article is irradiated with a source of fast neutrons, and fast neutrons released by the fissile or fissionable material, if present, are detected between source neutron pulses. The method uses a neutron detector that can detect and discriminate fast neutrons in the presence of thermal neutrons and gamma radiation. The detector is able to process high count rates and is resistant to radiation damage, and is preferably a solid state neutron detector comprised of silicon carbide.

Abstract: Apparatus and methods for measuring radiation in a borehole environment using a YAlO3:Ce (YAP) scintillation crystal. Borehole instruments are disclosed which employ a gamma ray detector comprising a YAP scintillator coupled to a light sensing means such as a photomultiplier tube. One instrument embodiment combines a YAP scintillation detector and a source of pulsed neutrons. Borehole environs are irradiated with neutrons, and induced gamma radiation is measured using a YAP scintillation detector. Response of the detector is used to determine characteristics of the borehole environs. Mechanical and physical properties of YAP are utilized to obtain improved measurements. The relatively short light decay constant of YAP minimized pulse pile-up in the detector when measurements require that the detector be operated during a neutron pulse.

Abstract: A material analyzer for identifying quantities of one or more elements in a material has a container for holding a material to be analyzed, a resonant gamma ray source unit for directing resonant gamma rays into the material in the container, and at least one detector for detecting gamma rays resonantly scattered by at least one predetermined element in the material. The resonant gamma ray source unit has an outer housing of gamma ray shield and neutron shield material, with an inner chamber and an aperture directed towards the container, a moving gamma ray generator source of a predetermined material mounted in the chamber, the material being selected from a predetermined group of materials which emit resonant gamma rays when exposed to neutrons, the source being directed towards said aperture, and a neutron source positioned in the chamber adjacent the gamma ray generator source.

Abstract: An ion source has an extraction system configured to produce ultra-short ion pulses, i.e. pulses with pulse width of about 1 ?s or less, and a neutron source based on the ion source produces correspondingly ultra-short neutron pulses. To form a neutron source, a neutron generating target is positioned to receive an accelerated extracted ion beam from the ion source. To produce the ultra-short ion or neutron pulses, the apertures in the extraction system of the ion source are suitably sized to prevent ion leakage, the electrodes are suitably spaced, and the extraction voltage is controlled. The ion beam current leaving the source is regulated by applying ultra-short voltage pulses of a suitable voltage on the extraction electrode.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer for aircraft is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of tantalum. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A method for detecting an explosive in an object under investigation involves the initial X-ray irradiation of the object under investigation, e.g. a piece of luggage or mailing, and forming its X-ray images; using the X-ray images to detect areas with a high density of organic materials and identifying articles therein; determining the location, dimensions and supposed mass of an unidentified article; determining and forming a directional pattern of the neutron radiator corresponding to the dimensions of the unidentified article. The method further includes subsequent thermal neutron irradiation of the area with the unidentified article; recording gamma-ray quanta having the energy of 10.8 MeV and cascade gamma-ray quanta with energies of 5.534 and 5.

Abstract: A neutron generator includes a modular arrangement of a high current electron bombardment ion source, providing deuterium(D) and/or tritium(T) ions, a high voltage acceleration stage to accelerate the ions and raise the ion energy to the order of 100 keV, and an occluded reaction target containing T and/or D to produce the nuclear reactions. Neutrons are produced in the target using the D—D and/or D-T reaction. The invention is designed to allow the target to be located at the end of a needle and thereby is useful for treating cancers by the Brachy therapy method. The ion source of the neutron generator is a modified version of the electron bombardment type used in mass spectrometers for gas analysis. This source uses an electron beam running through an ionization chamber to ionize gas molecules that are extracted out of the chamber by electric fields.

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: An ion source has an extraction system configured to produce ultra-short ion pulses, i.e. pulses with pulse width of about 1 &mgr;s or less, and a neutron source based on the ion source produces correspondingly ultra-short neutron pulses. To form a neutron source, a neutron generating target is positioned to receive an accelerated extracted ion beam from the ion source. To produce the ultra-short ion or neutron pulses, the apertures in the extraction system of the ion source are suitably sized to prevent ion leakage, the electrodes are suitably spaced, and the extraction voltage is controlled. The ion beam current leaving the source is regulated by applying ultra-short voltage pulses of a suitable voltage on the extraction electrode.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A method of preparing high-specific-activity 195mPt includes the steps of: exposing 193Ir to a flux of neutrons sufficient to convert a portion of the 193Ir to 195mPt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce 195mPt.

Abstract: A magnet for use with a neutron scattering apparatus. The neutron scattering apparatus provides an incident beam of neutrons to a sample under analysis. The magnet has first and second body portions of high conductivity material and has a mid-plane portion there between in which the sample under analysis is positioned. The first and second body portions of the coil are electrically connected to each other via the mid-plane portion of the coil between the body portions of the coil. The conductive mid-plane portion has a split that allows neutron scattering through large angles.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of titanium. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

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 neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer for aircraft is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of aluminum. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of titanium. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: The invention relates to nuclear physics and can be used for neutralizing long-lived radioactive isotopes contained, for example, in radioactive waste (RW) of the nuclear engineering. A radioactive isotope undergoes exposure to electromagnetic radiation and a deep ionization of the isotope atoms is performed. Deep ionization of the atoms results in an energy-permitted expedient B-decay thereof prohibited in a neutral state. Measures are taken in order to prevent ionized atoms from recombination with short-lived nucleus. The retention time must be long enough to transmit at least a part of the parent nucleus into the short-lived and stable daughter nucleus. For ensuring a factor k of an operating time of said daughter nucleus, the retention is performed at least during a time Ki, i is a life time of the parent nucleus at the expedient B-decay. A charge-particle beam (electrons, protons or ions) is used for electromagnetic irradiation.

Abstract: A neutron spectrometer for spacecraft is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of aluminum. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: The present invention relates to a method and portable apparatus which is used to detect substances, such as explosives and drugs, by neutron irradiation. The apparatus has a portable neutron generating probe and corresponding controllers and data collection computers. The probe emits neutrons in order to interrogate an object. The probe also contains gamma ray detectors for the collection of gamma rays from fast neutron, thermal neutron and neutron activation reactions. Data collected from these detectors is sent to the computer for data de-convolution then object identification in order to determine whether the object being interrogated contains explosives or illicit contraband.

Abstract: Thermal neutron irradiation of superconducting body compositions into which Li or B has been incorporated as a unit cell external or internal dopant introduces by the nuclear reaction of the dopant pinning centers which substantially improve the critical current density of the body.

Abstract: A neutron detection system for detection of contaminants contained within a bulk material during recycling includes at least one neutron generator for neutron bombardment of the bulk material, and at least one gamma ray detector for detection of gamma rays emitted by contaminants within the bulk material. A structure for analyzing gamma ray data is communicably connected to the gamma ray detector, the structure for analyzing gamma ray data adapted. The identity and concentration of contaminants in a bulk material can also be determined. By scanning the neutron beam, discrete locations within the bulk material having contaminants can be identified.

Abstract: This application relates to devices and methods for locally delivering therapeutic radiation to tissue in the body of a patient. In certain embodiments, the subject devices are implanted into a cavity in the patient left by surgical removal of tumorous tissue or other diseased tissue, to deliver radiation to the tissue surrounding the cavity. In certain embodiments, the devices are elastic or can otherwise be shaped to conform to the shape of the cavity in the patient.

Abstract: The method comprises the steps of forming an elongated tubular metal casing 1. This elongated tubular metal casing 1 is then coiled. The coiled tubular casing 11 is filled with a material 9 capable to irradiate radioactive radiation. The material 9 is in liquid state with following crystallization in the coiled tubular casing 11. The filled coiled tubular casing 11 is then sealed at its ends 5.

Abstract: The invention relates to an analyzer for the identification of explosives and/or chemical warfare agents, with a neutron source which causes the emission of characteristic &ggr; quanta, whereby the analysis system consists of a mobile frame to which a neutron source and a detector as well as a holder for the object are attached, with a neutron generator which contains deuterium as the target, generates neutron pulses by periodically repeated, pulsed bombardment of the target and is controlled so that short neutron pulses are emitted and repeated periodically, whereby the detector is controlled so that in cycles it detects &ggr; quanta promptly emitted from the object due to inelastic neutron scattering and neutron capture, within at least two consecutive temporal measurement windows, whereby the first measurement window at least partially overlaps temporally the neutron pulse and the subsequent second measurement window does not, whereby in the first measurement window &ggr; quanta are essentially detected du

Abstract: A fullerene molecule having one or more free thermal neutrons trapped within the fullerene molecule and a method for trapping and storing neutrons within a fullerene molecule are described.