9results about "Subcritical reactors" patented technology

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

The invention relates to a design method of a four-proton beam ADS device, and the method comprises the steps: building a reactor model which comprises a shielding layer, a reflecting layer, a fuel region and a heavy metal target; the heavy metal target comprises a central heavy metal target and three surrounding heavy metal targets; two accelerators are arranged for the heavy metal target and are respectively a first accelerator used for bombarding the central heavy metal target and a second accelerator used for bombarding the three surrounding heavy metal targets in turn so as to generate a four-proton beam; establishing an exogenous disturbance point reactor neutron kinetic equation; obtaining dynamic parameters in the reactor model based on the reactor model and the accelerator; determining a power upper limit of the reactor model based on the temperature limit value of each structure in the reactor model; the temperature limit value of each structure is based on the temperature corresponding to the melting point of the material of each structure; and if the reactor power exceeds the power upper limit, adjusting the structure parameters of the reactor model and the operation parameters of the accelerator.

To provide a fusion-driven subcritical reactor that is more efficient and safer. [Solution] A fusion-driven subcritical reactor is a nuclear reactor that starts and operates by amplifying neutrons obtained from nuclear fusion and supplying the amplified neutrons to a reactor that holds subcritical nuclear fuel by external neutrons. It consists of a main neutron source that generates DD neutrons through a nuclear fusion reaction, a cascade member that surrounds the main neutron source, separates fusion / fission neutrons, multiplies the fast fission neutrons generated by nuclear fission, and slows down the fast fission neutrons, and a cascade member that surrounds the cascade member and is mainly made of thorium oxide ( 232 It is equipped with a subcritical main fission blanket made of uranium dioxide (ThO2), and a neutron flattening blanket that has a neutron source located around the outer periphery of the main fission blanket to improve the containment of fission neutrons.

The present invention discloses a rapid automated modeling method, system, and medium applicable to research reactors, and belongs to the field of thermal hydraulic technology of research reactors. The method includes: establishing position numbers for different positions of the reactor core; establishing coordinates under the position numbers; collecting layout information of components in the reactor core, establishing coordinate information of components in the reactor core; establishing component structured data corresponding to the positions; sequentially reading information of each position of the reactor core, establishing a component model of the entire reactor core, and completing rapid automated modeling of the entire core. The rapid automated modeling method applicable to research reactors provided by the present invention models and analyzes each type of component in the core (including beryllium components, fuel components, aluminum components, control rod components, and irradiation channels) separately, and finally establishes a one-to-one corresponding position assembly relationship for the core layout in a programming manner, thereby realizing three-dimensional automatic modeling.

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

The application relates to a design method of a four-proton beam flow ADS device, which comprises the following steps: establishing a reactor model, wherein the reactor model comprises a shielding layer, a reflecting layer, a fuel area and a heavy metal target; the heavy metal target comprises a central heavy metal target and three surrounding heavy metal targets; arranging accelerators for the heavy metal target, wherein the accelerators are provided in two, and are respectively a first accelerator for bombarding the central heavy metal target and a second accelerator for alternately bombarding the three surrounding heavy metal targets, so as to generate a four-proton beam flow; establishing an external source disturbance point reactor neutron dynamics equation; obtaining dynamic parameters in the reactor model based on the reactor model and the accelerators; determining a power upper limit of the reactor model based on temperature limits of each structure in the reactor model; the temperature limit of each structure is a temperature corresponding to a melting point of a material of each structure; and if the reactor power exceeds the power upper limit, adjusting structure parameters of the reactor model and operation parameters of the accelerators.

Device for reducing spent nuclear fuel, comprising a container for receiving nuclear fuel, wherein the device is configured to transmute long-lived radioisotopes of the nuclear fuel into radioisotopes having a significantly shorter half-life than the initial radioisotopes by interaction with fast neutrons.

Device which is configured to hold a nuclear fuel and has one or more neutron sources which are configured to emit free neutrons which can interact with isotopes of the nuclear fuel, wherein the one or more neutron sources are configured such that the neutron flux strength of the generated neutrons is more than 10 12 neutrons per second and the one or more neutron sources have a power supply by means of which the neutron flux strength can be controlled.