Abstract: Provided are a long-lived target for a neutron-generating device and a method for manufacturing the target therefore. The target is for a neutron-generating device and includes: a metal substrate retaining a target material; and a metal thin film for sealing that holds the target material at a retention surface X side. The retention surface X side of the metal substrate includes: a frame portion; and an embossed structure including: a plurality of island portions that are surrounded by the frame portion; and the rest recessed portion that is created by decreasing a thickness of a region other than the frame portion and the island portions by a thickness of the target material. The metal thin film and surfaces of the frame portion and the island portions are subjected to hot isostearic pressing (HIP) bonding to seal the target material onto the recessed portion by using the metal thin film.

Abstract: A tritium production element for use in a conventional power reactor, and methods of use and making, are provided, wherein the element experiences reduced tritium permeation during irradiation by incorporating a silicon carbide barrier that encapsulates one or more burnable absorber pellets. The tritium production element includes a tubular cladding that encloses a plurality of burnable absorber pellets, such that individual pellets or groups of pellets are disposed within a silicon carbide barrier layer.

Abstract: Methods of producing cesium-131. The method comprises dissolving at least one non-irradiated barium source in water or a nitric acid solution to produce a barium target solution. The barium target solution is irradiated with neutron radiation to produce cesium-131, which is removed from the barium target solution. The cesium-131 is complexed with a calixarene compound to separate the cesium-131 from the barium target solution. A liquid:liquid extraction device or extraction column is used to separate the cesium-131 from the barium target solution.

Abstract: A liquid lithium jet nozzle comprising: an inlet through which liquid lithium flows into the nozzle; an inlet flow channel that receives liquid lithium that flows into the nozzle via the inlet and shapes the flowing liquid lithium to flow in a thin film; and a flow region that receives flowing liquid lithium shaped by the flow channel and in which the liquid lithium flows with at least one large surface of the film exposed.

Abstract: Disclosed are apparatus and method of providing accurate control of a nuclear reactor containing fuel and designed to be subcritical in the static case that has a vessel, the vessel defining a shell, and an internal volume containing the fuel. A fusion target is located in the internal volume and contains a reactive material. A pulsed source of a hydrogen isotope directs the hydrogen isotope into, but stopping within the fusion target. Each pulse of a hydrogen isotope produces a pulse of neutrons from the reactive material in the fusion target that scatter into and burn the fuel, and thereafter the reactor returns to the static case.

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 means for and method of producing and retaining tritium utilizing lithium bismuth and nickel is disclosed herein. The lithium bismuth serves to produce the tritium when exposed to neutrons. The nickel serves to dissolve and thereby retain the tritium which is produced by the lithium bismuth. As disclosed herein, both of these materials are contained within a common tubular housing which is pervious to the neutrons but impervious to any tritium which is produced therein.

Abstract: A method and apparatus are described for the joint production and separation of tritium. Tritium is produced in an aqueous homogenous reactor and heat from the nuclear reaction is used to distill tritium from the lower isotopes of hydrogen.

Abstract: A nuclear fuel assembly is described for producing tritium in a light water moderated reactor. The assembly consists of two intermeshing arrays of subassemblies. The first subassemblies comprise concentric annular elements of an outer containment tube, an annular target element, an annular fuel element, and an inner neutron spectrums shifting rod. The second subassemblies comprise an outer containment tube and an inner rod of either fuel, target, or neutron spectrum shifting neutral.

Abstract: A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.