Provided herein are systems and methods for generating a plurality of different monoenergetic neutron energies using a plurality of interchangeable ion beam targets. In certain embodiments, each of the plurality of ion beam targets is configured to generate a monoenergetic energy value that is at least 100 kiloelectron volts (keV) different from the other ion beam targets. In some embodiments, the ion beam targets are composed of LiF, TiT.sub.1-2, ErD.sub.1.5, ErT, or Li.

A system and method for performing active scanning on a nuclear fuel rod are provided. The system includes an electrically-driven neutron generator including an ion source, an accelerator, and a target; a moderator surrounding the neutron generator and configured to moderate neutrons generated by the neutron generator; a fuel rod channel disposed within the moderator, the fuel rod channel configured to receive a nuclear fuel rod and subject the nuclear fuel rod to a predetermined neutron flux; and a plurality of radiation detectors. When the nuclear fuel rod is subjected to the predetermined neutron flux, neutrons induce a secondary radiation of prompt and delayed gamma emissions, neutron emission, or a combination thereof that are detected by the plurality of radiation detectors to determine an amount of fissile material in the nuclear fuel rod and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

Radiating device (1) comprising at least one vacuum chamber (2), an electrostatic accelerator or laser of high power and high frequency (5) for producing at least one primary beam inside the vacuum chamber (2), and an active material layer (4) carried by a support (3) into the vacuum chamber (2) to generate an intense neutron flux when the active layer is struck by the primary beam, and at least one target (6) comprising a material, with the target (6) disposed on the same side of the electrostatic accelerator or power laser (5) as the active material layer (4).

A well logging tool includes a neutron generator to generate and emit energetic neutrons using substantially exclusively a T-T fusion reaction. The well logging tool can include measuring instrumentation for measurement and logging of formation parameters based on elastic scattering in subsurface formations of neutrons emitted by the neutron generator. The neutron generator can have a concentric layout, in which a cylindrical target structure loaded with tritium particles is located co-axially in an elongate cylindrical housing, with mobile tritium ions being accelerated radially inwardly into impact with the target structure. Production of the mobile tritium ions may be by field ionization through operation of a nano-structure field ionization array.

Embodiments that are directed to a target for producing a high epithermal neutron yield for boron-neutron capture therapy (BNCT) treatments are disclosed. The target includes a thin flat film of solid lithium mounted onto a heat-removal support structure that is cooled with a liquid coolant and configured to maintain the turbulent flow regime for a liquid coolant and distribute the flow of coolant directed at the center of the support structure toward a periphery of the support structure via a plurality of channels formed in the support structure. The support structure includes a nozzle located at its center to direct coolant flow outwardly from the center to avoid stagnant water flow at the center of the support structure. Systems, device, and methods utilizing the approaches are also described.

Embodiments that are directed to a target for producing a high epithermal neutron yield for boron-neutron capture therapy (BNCT) treatments are disclosed. The target includes a thin flat film of solid lithium mounted onto a heat-removal support structure that is cooled with a liquid coolant and configured to maintain the turbulent flow regime for a liquid coolant and distribute the flow of coolant directed at the center of the support structure toward a periphery of the support structure via a plurality of channels formed in the support structure. The support structure includes a nozzle located at its center to direct coolant flow outwardly from the center to avoid stagnant water flow at the center of the support structure. Systems, device, and methods utilizing the approaches are also described.

The invention relates generally to nuclear engineering and more particularly to controlled reactor start-up. The invention improves reliability of an operational neutron source by creating additional safety barriers between the coolant and the source active part materials. The operational neutron source is designed as a steel enclosure housing an ampule containing antimony and beryllium with separate antimony and beryllium cavities positioned coaxially. The antimony is contained in the central enclosure made of a niobium-based alloy unreactive with antimony. A beryllium powder bed is located between the antimony enclosure and the ampule enclosure. The ampule enclosure is made of martensite-ferrite steel poorly reacting with beryllium. An upper gas collector is located above the ampule, which serves as a compensation volume collecting gaseous fission products. At the bottom, the ampule is supported by a reflector and a bottom gas collector. The gas collectors, reflector and washers are made of martensite-ferrite grade steel.

The invention relates generally to nuclear engineering and more particularly to controlled reactor start-up. The invention improves reliability of an operational neutron source by creating additional safety barriers between the coolant and the source active part materials. The operational neutron source is designed as a steel enclosure housing an ampule containing antimony and beryllium with separate antimony and beryllium cavities positioned coaxially. The antimony is contained in the central enclosure made of a niobium-based alloy unreactive with antimony. A beryllium powder bed is located between the antimony enclosure and the ampule enclosure. The ampule enclosure is made of martensite-ferrite steel poorly reacting with beryllium. An upper gas collector is located above the ampule, which serves as a compensation volume collecting gaseous fission products. At the bottom, the ampule is supported by a reflector and a bottom gas collector. The gas collectors, reflector and washers are made of martensite-ferrite grade steel.

The present invention provides a neutron generating device for generating a high neutron flux by forming plasma in the vicinity of a target and by accelerating electrons and charged particles in the plasma toward the target. Magnetic field is formed in the vicinity of the target and a microwave generator irradiates microwaves into the space where the magnetic field is generated to thereby generate plasma in the space. The accelerated electrons and charged particles collide with the target to generate neutron flux. Also, to prevent the target surface from being excessively heated, the plasma is generated in a pulsed mode and target voltage is applied in a pulsed mode. To secure a continuous process, the level of target bias voltage for the target is adjusted so that the target re-adsorbs elements when the elements adsorbed on the target are depleted.

The present invention provides a neutron generating device for generating a high neutron flux by forming plasma in the vicinity of a target and by accelerating electrons and charged particles in the plasma toward the target. Magnetic field is formed in the vicinity of the target and a microwave generator irradiates microwaves into the space where the magnetic field is generated to thereby generate plasma in the space. The accelerated electrons and charged particles collide with the target to generate neutron flux. Also, to prevent the target surface from being excessively heated, the plasma is generated in a pulsed mode and target voltage is applied in a pulsed mode. To secure a continuous process, the level of target bias voltage for the target is adjusted so that the target re-adsorbs elements when the elements adsorbed on the target are depleted.