8 results about "Subcritical reactor" patented technology

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.

This invention relates to the technical field of nuclear reactor waste treatment, and discloses a method, electronic device, and storage medium for locking transmutation MA fuel schemes in an ADS system. The method includes: acquiring basic parameter inputs, target core subcriticality inputs, and experimental data; extracting database parameters and summarizing and fitting them to obtain processed database parameters; generating composition parameter files and mass parameter files; calculating the core subcriticality; comparing the core subcriticality with the target core subcriticality, and if the relative error is less than a preset error value, locking the transmutation MA fuel composition scheme corresponding to the experimental data. This method improves computational efficiency, reduces related computational energy consumption, simplifies research procedures, avoids a large number of invalid calculations in the research, reduces human error, and improves the efficiency of locking transmutation MA subcritical reactor fuel schemes in an ADS system.

The invention discloses a multi-treatment-room boron neutron capture therapy system based on an external source driven subcritical reactor core, and particularly relates to the technical field of medical science, the multi-treatment-room boron neutron capture therapy system comprises an external neutron source, the external neutron source comprises a charged particle transport section and a charged particle targeting section, the charged particle transport section is used for accelerating and transporting charged particles, and the charged particle targeting section is used for targeting the charged particles; and the charged particle targeting section is connected with the charged particle transport section, so that the charged particles react with the target material to release primary neutrons. According to the boron neutron capture therapy system, multiplication and fission of an initial neutron source can be achieved, the neutron flux level needed by a therapy beam is greatly improved, meanwhile, the system is in a subcritical state, rapid closing of the system can be achieved by cutting off charged particle beams, the possibility of instant supercritical safety accidents is completely eradicated, and the service life of the system is prolonged. And a synchronous multi-terminal boron neutron capture treatment function can be realized, the number of cancer patients treated every year is remarkably increased, and meanwhile, the treatment cost is remarkably reduced.

The present invention discloses a heat exchange-reaction integrated super-subcritical water oxidation reactor and method. The reactor includes an outer cylinder, an inner cylinder, and a lower support plate therein. A water storage chamber is formed between the lower support plate and the bottom of the outer cylinder. The interior of the inner cylinder is divided into a catalytic reaction zone and a preheating heat exchange zone by the upper support plate. The preheating heat exchange zone is provided with a plurality of heat exchange tubes arranged in an array. The upper ends of the heat exchange tubes are connected to the catalytic reaction zone, and the lower ends of the heat exchange tubes are connected to the water storage chamber. The lower end of the central guide tube is connected to the preheating heat exchange zone, and the upper end of the central guide tube upwardly passes through the catalyst bed in the catalytic reaction zone. The outer cylinder is provided with a material inlet and a material outlet. The raw material liquid introduced from the material inlet can enter the preheating heat exchange zone and contact the outer wall of the heat exchange tube for heat exchange. The present invention combines a conventional heat exchanger and a super-subcritical reactor into an independent structure that integrates heat exchange and oxidation reaction functions, occupies a small area, and reduces the price of reactor materials.

An example for continuous removal of fission products from a molten-salt fueled nuclear reactor enclosed in a reactor containment may include separating actinides from other fission products flowing out of the reactor, returning the separated actinides back to the reactor to be consumed, and removing the other fission products out of the containment while the reactor is operating. In various embodiments, the reactor can be a critical reactor, a subcritical (e.g., accelerator-drive) reactor, or another type of reactor.

The application discloses a high-temperature lead-bismuth alloy experimental system with an additional heat storage device for heat preservation. The experimental system utilizes the heat generated by a subcritical reactor, adopts pressurized water as a heat transfer fluid of a secondary loop to exchange heat with a primary loop and carries out experiments. In the case that the system stops the experiments, liquid lead-bismuth alloy is pumped into a lead-bismuth alloy storage tank, and the heat stored by the heat storage device is used to heat the lead-bismuth alloy storage tank. The application solves the problems in the prior art by adding the heat storage device, such as the need of consuming a large amount of electric energy to install an electric auxiliary heating device on a lead-bismuth alloy pipeline to maintain the temperature of the lead-bismuth alloy pipeline. In addition, the application has the advantages of high energy utilization efficiency, no additional power consumption and the like. Meanwhile, the application can provide reliable and stable experimental support for the research and development of heat storage / exchange devices in compressed air energy storage systems and the like, and provide technical support for the clean, safe and efficient utilization of nuclear energy.

A device for treating organic waste by subcritical water pyrolysis, characterized by two parallel subcritical reactors, the upper surfaces of which are each connected to a feed opening that directs the organic waste material into the reactors. The two reactors are arranged to the left and right, with a support frame between them. The upper surface of this frame includes a pretreatment unit connected to the feed opening via piping. The pretreatment unit comprises a stirring chamber, the upper surface of which is connected to a filter via a flange. A pressure feed device containing a feed chamber is located on the top of the filter. The upper surface of the feed chamber is connected to a feed pipe, the lower part of which is connected to a corrugated pipe located inside the feed chamber.A pressure plate is attached to the end of the corrugated tube, and this plate has an opening corresponding to the tube's outlet. An electromagnetic valve is installed in this opening. A lifting device is mounted on the outside of the feed chamber, allowing the pressure plate to move vertically.

This invention discloses a method and system for optimizing the decay cooling time of fuel assemblies after subcritical reactor operation. The optimization method includes: obtaining the shortened time to resume fuel operation after reactor shutdown; analyzing the radioactive consequences of a fuel operation accident through modeling based on the time to resume fuel operation after shutdown, and determining whether a first preset condition is met; analyzing the cooling capacity of the spent fuel pool through modeling based on the time to resume fuel operation after shutdown, and determining whether a second preset condition is met; analyzing the radiation shielding of the fuel building through modeling, and determining whether a third preset condition is met; and when all three preset conditions are met, using the time to resume fuel operation after shutdown as the decay cooling time of the fuel assemblies after subcritical operation. Implementing this invention allows for the direct reduction of the fuel assembly decay cooling time requirement before overhaul unloading without requiring physical modifications.