A molten salt reactor system includes a fluid level control system configured to circulate a molten salt through a molten salt loop including an experimental tank, a sump tank, and a drain tank. The fluid level control system further includes a plurality of level sensors, pressure transducers, and electronic pressure regulators fluidically coupled with the fuel salt system. The fluid level control system is configured to receive cover gas pressures in the headspaces of the tanks and calculate target fluid height setpoints for each of the tanks. The fluid level control system further invokes the electronic pressure regulator to iteratively adjust the cover gas pressures of the tanks to achieve and maintain a target fluid level in the experimental tank.

A fuel assembly (1) for a nuclear power plant includes at least one hollow rod (9, 9a,9b, 9c). The hollow rod is a control rod guide tube (9) of the fuel assembly (1) for the control rod assembly or an instrumentation tube. Each rod (9) is adapted to be filled with one or more containers (38) filled with material to be activated. The fuel assembly further comprises a damping element (36, 36a, 36b, 36c) at the lower end (32) of the hollow rod (9, 9a,9b, 9c).

Irradiation target holders are configured to fit in open locations inside of an operating commercial nuclear core. Holders can be placed with ends at vertical bottom and top of the core or any position therebetween to directly expose holders to nuclear fuel reactions. Holders have ends and overall shape that can join with existing reactor structures, while fitting closely with fuel and moderator and being easily removable from the same. Holders are fabricated of any reactor-compatible material that will retain irradiation targets and daughter products. Holders securely retain irradiation targets and daughter products of any shape or phase throughout reactor operation. Holders can be installed during reactor outages and irradiated during operation without risk of movement or interference with operation. After a desired period of operation and irradiation, holders can be harvested from the core independent of other core structures and fuel.

An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.

Fissile target materials are provided. The fissile target materials can include a target substrate and a capturing layer operably interfacing with at least one surface of the target substrate. Fission fissile target materials are also provided that can include a target substrate comprising at least one fissile atom and a capturing layer operably interfacing with at least one surface of the target substrate. The capturing layer can include at least one fission product.

Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons 0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.

Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons 0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.

A core component assembly for insertion into a fuel assembly of a nuclear reactor is disclosed. The core component assembly includes a baseplate, a connector, and a crimp nut. The baseplate includes a first side and a second side. An aperture is defined through the baseplate between the first side and the second side. The connector includes a bayonet, a threaded portion disposed beneath the bayonet, an annular shoulder disposed beneath the threaded portion, a gripping area disposed beneath the annular shoulder, and a hole disposed beneath the gripping area. The crimp nut includes a crimp sleeve and a threaded opening and is aligned with the aperture of the baseplate and welded to the first side of the baseplate. The threaded portion of the connector is threaded into the threaded opening of the crimp nut to attach the connector to the baseplate and position the bayonet within the crimp sleeve.

A core component assembly for insertion into a fuel assembly of a nuclear reactor is disclosed. The core component assembly includes a baseplate, a connector, and a crimp nut. The baseplate includes a first side and a second side. An aperture is defined through the baseplate between the first side and the second side. The connector includes a bayonet, a threaded portion disposed beneath the bayonet, an annular shoulder disposed beneath the threaded portion, a gripping area disposed beneath the annular shoulder, and a hole disposed beneath the gripping area. The crimp nut includes a crimp sleeve and a threaded opening and is aligned with the aperture of the baseplate and welded to the first side of the baseplate. The threaded portion of the connector is threaded into the threaded opening of the crimp nut to attach the connector to the baseplate and position the bayonet within the crimp sleeve.

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.