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, TiD.sub.1.5-1.8, TiT.sub.1-2, ErD.sub.1.5, ErT, or Li.

The present invention discloses a compact integrated deuterium-deuterium (D-D) neutron generator. A hemispherical metal head is disposed inside a cylindrical ceramic shell of the generator and is provided therein with an ion source and an ion source power supply. An inner ceramic insulated cylinder and an outer ceramic insulated cylinder are disposed between a metal plate of the metal head and a baseplate of the generator, and an isolated power supply system and a high-voltage power supply are disposed between the inner ceramic insulated cylinder and the outer ceramic insulated cylinder. A rear end of an extraction accelerating electrode disposed inside the inner ceramic insulated cylinder protrudes from the generator and is then connected to a target holder disposed outside the baseplate. A target is disposed inside the target holder, the target is at ground potential, and a cooling water interface is disposed on the target holder.

The present invention discloses a compact integrated deuterium-deuterium (D-D) neutron generator. A hemispherical metal head is disposed inside a cylindrical ceramic shell of the generator and is provided therein with an ion source and an ion source power supply. An inner ceramic insulated cylinder and an outer ceramic insulated cylinder are disposed between a metal plate of the metal head and a baseplate of the generator, and an isolated power supply system and a high-voltage power supply are disposed between the inner ceramic insulated cylinder and the outer ceramic insulated cylinder. A rear end of an extraction accelerating electrode disposed inside the inner ceramic insulated cylinder protrudes from the generator and is then connected to a target holder disposed outside the baseplate. A target is disposed inside the target holder, the target is at ground potential, and a cooling water interface is disposed on the target holder.

The present disclosure is directed to systems for generating neutrons, the systems including a stellarator optimized for fast particle finement. In some embodiments, the stellarator optimized for fast particle confinement is selected from a quasi-axisymmetric stellarator, a quasi-symmetric stellarator, a quasi-isodynamic stellarator, or a quasi-omnigenous stellarator. The present disclosure is also directed to methods of generating neutrons using the systems of the present disclosure and, in particular, systems incorporating a stellarator optimized for fast particle confinement.

The present disclosure is directed to systems for generating neutrons, the systems including a stellarator optimized for fast particle finement. In some embodiments, the stellarator optimized for fast particle confinement is selected from a quasi-axisymmetric stellarator, a quasi-symmetric stellarator, a quasi-isodynamic stellarator, or a quasi-omnigenous stellarator. The present disclosure is also directed to methods of generating neutrons using the systems of the present disclosure and, in particular, systems incorporating a stellarator optimized for fast particle confinement.

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.

Provided herein are neutron-based detection systems and methods that provide, for example, high throughput analysis of elemental analysis of scrap materials. Such systems and methods find use for the commercial-scale evaluation of bulk process materials where hazardous or otherwise undesirable materials or high value materials may be interspersed with the primary process material. In certain embodiments, the system is used to detect and potentially remove unexploded ordinance (UXO) from a conveyor of demilitarized shell casings being recycled by detecting the presence of nitrogen and other elements present in the UXO. In other embodiments, the system detects and removes unwanted or highly valuable materials from a stream of scrap material.

The present disclosure provides a neutron capture therapy system, including an accelerator for generating a charged particle beam, a neutron generator for generating a neutron beam having neutrons after irradiation by the charged particle beam, and a beam shaping assembly for shaping the neutron beam. The beam shaping assembly includes a moderator and a reflecting assembly surrounding the moderator. The neutron generator generates the neutrons after irradiation by the charged particle beam. The moderator moderates the neutrons generated by the neutron generator to a preset energy spectrum. The reflecting assembly includes a reflecting assembly to deflected neutrons back to the neutron beam and a supporting member to support the reflectors. A lead-antimony alloy is for the reflecting assembly to mitigate a creep effect that occurs when only a lead material is for the reflectors, thereby improving the structural strength of a beam shaping assembly.

The present disclosure provides a neutron capture therapy system, including an accelerator for generating a charged particle beam, a neutron generator for generating a neutron beam having neutrons after irradiation by the charged particle beam, and a beam shaping assembly for shaping the neutron beam. The beam shaping assembly includes a moderator and a reflecting assembly surrounding the moderator. The neutron generator generates the neutrons after irradiation by the charged particle beam. The moderator moderates the neutrons generated by the neutron generator to a preset energy spectrum. The reflecting assembly includes a reflecting assembly to deflected neutrons back to the neutron beam and a supporting member to support the reflectors. A lead-antimony alloy is for the reflecting assembly to mitigate a creep effect that occurs when only a lead material is for the reflectors, thereby improving the structural strength of a beam shaping assembly.