5 results about "Fast-neutron reactor" patented technology

A compact, liquid-metal cooled, loop-type, fast neutron reactor. The invention relates to a primary / secondary heat exchanger with identical loops, each consisting of a heat transfer module arranged axisymmetrically around the reactor block. Each module comprises an expansion tank (20), a heat exchanger (21), and an electromagnetic pump (22), which alone forms a heat exchange loop between the liquid sodium primary circuit and the gaseous secondary circuit, such as nitrogen, which is a closed Brayton cycle. Figure for the abstract: Fig. 11

This invention relates to the field of nuclear reactors, specifically to a lead-based fast neutron reactor exhaust device and a fission gas collection device. The exhaust device includes fuel rods and a one-way exhaust device. The fuel rods include nuclear fuel pellets and cladding tubes. The one-way exhaust device connects the gas chamber to the outside of the cladding tubes in one direction. A metal coolant is provided inside the pressure vessel to submerge the fuel rods and the one-way exhaust device. In use, the fission gas generated by the nuclear fuel pellets passes through the one-way exhaust device and enters the metal coolant in one direction. The fission gas collection device includes a lead-based fast neutron reactor exhaust device, a temporary storage tank, a multi-stage purification device, and a circulation pump. This invention achieves the purpose of one-way exhaust by connecting a one-way exhaust device to the cladding tube of the fuel rods, so that the fission gas inside the fuel rods is discharged into the primary coolant when the pressure exceeds a certain level. The fission gas collection device collects gaseous fission products in the upper chamber of the reactor pressure vessel.

A nuclear power plant with a nuclear building housing at least one molten salt fast neutron reactor and a fission gas management system for the accumulated gases in the reactor pile headspace. The invention relates to a nuclear power plant comprising: a reactor building (10); at least one reactor vessel shaft (9), located inside the reactor building; at least one reactor vessel (2) (1) filled with a molten salt fuel bath and defining within it a gas space above the free level of the bath, called the pile headspace; another vessel (8), arranged around the reactor vessel and inside the reactor vessel shaft, defining an inter-vessel space (E) with the reactor vessel; at least one fission gas management system (gaseous PF) for the gases accumulated in the reactor vessel pile headspace during normal reactor operation. Figure for the abstract: Fig. 2

This invention belongs to the field of nuclear reactor core design, specifically relating to a method for constructing an equivalent model of the non-fuel region of a fast neutron reactor with complex geometry. First, the core of the three-dimensional fast neutron reactor to be simulated is geometrically divided into several layers along the axial direction. For each layer, a fine-group embedding self-screen resonance model is established. Then, the material of all fuel regions in the core is homogenized and used as average fuel. This average fuel is constructed outside the cylindrical model of the non-fuel region, ensuring that the non-fuel nuclides calculated by the cylindrical model are consistent. n The escape cross section is conserved with the escape cross section calculated by resonance, and an equivalent model of the outermost fuel radius is iteratively searched. Its advantages are: this method can quickly and online obtain the equivalent model of each non-fuel zone in the reactor core; it offers excellent geometric flexibility for complex reactor cores, fully considers environmental effects, and has higher computational accuracy; it can be used for rapid simulation calculations of numerical reactors and engineering applications.

The invention consists essentially of a fuel assembly (1) of hexagonal or parallelepiped cross-section, without a hexagonal duct, preferably intended for low-power-density sodium-cooled fast neutron reactors (SFR).