40 results about "Fission reactor" patented technology

The invention relates to a fission reactor criticality calculation system based on a Monte Carlo method. The fission reactor criticality calculation system comprises a grid numerical analysis module, a shannon entropy calculation module and a shannon entropy evaluation module. The system is implemented through the following steps of: firstly, resolving grid partition information filled in an input file by a user, then calculating shannon entropy of each generation according to a shannon entropy calculation formula, performing numerical correction on a shannon entropy curve, quantitatively giving algebra required by system source convergence, and automatically regulating non-active generation algebra in the system, wherein the shannon entropy evaluation module fits a shannon entropy curve according to the least square method, judges the algebra required by convergence by use of the corrected shannon entropy according to convergence condition, and then sets the non-active generation algebra of the system. According to the fission reactor criticality calculation system based on the Monte Carlo method, the restriction that the non-active generation algebra of a traditional fission reactor criticality calculation system is manually set by a user is changed, and the efficiency of calculating the fission reactor criticality by use of the Monte Carlo method is improved.

The invention provides a production method of a nuclear fuel clad element. The method comprises the following steps: selecting an MAX phase ceramic material, silicon carbide, an MAX phase-based composite ceramic material or a silicon carbide-based composite ceramic material, processing the above ceramic material to prepare a slurry, carrying out vacuum defoaming, making a ceramic film with the thickness of 10[mu]m-10mm on a base band through a curtain coating or draw-off process, winding to make a clad element blank, drying, carrying out rubber discharging, sintering, and carrying out surface treatment to obtain the nuclear fuel clad element. The production method has the advantages of simplicity, easy implementation, low cost, overcoming of the disadvantage of difficult processing of ceramic materials, high production efficiency, short cycle and easy industrialization. When the ceramic material is a Ti3SiC2-baed ceramic material, the ceramic material can resist molten fluorine salt corrosion, and can be used as a fluorine salt fuel clad element material in a nuclear reactor, so practical demands of a thorium-based fourth generation fission reactor nuclear energy system on the structure material are met.

The invention discloses a modeling system which is used in reactor design and used for reactor core component design. According to the modeling system, the geometric specificity of a fission reactor core is analyzed, a great amount of repeatedly constructed geometries are adopted, a CAD engineering model and a Monte Carlo calculation model of the fission reactor core are automatically established by establishing parameters, the Monte Carlo calculation model is used for radiating and transporting input of a Monte Carlo calculation program, and the significant physical quantity of the reactor core can be calculated after the Monte Carlo calculation model is obtained. By constantly evaluating the physical parameters of the calculation result, the modeling system can be used for performing repeated iteration correction on a design scheme of the fission reactor core till a reactor core scheme which makes a user satisfactory is made. The modeling system has the benefits that the tediousness that Monte Carlo calculation programs are written and files are input manually is avoided, the whole modeling process is very visible, the probability of mistakes is greatly reduced, and the design time of the reactor core is shortened.

The invention discloses a method for controlling the reactivity of a molten salt fission reactor. The molten salt fission reactor comprises a core including fuel tubes (103) containing molten salt fission fuel and coolant tanks (101) containing molten salt coolant (102), wherein the fuel tubes are submerged in the coolant in the slot. The method includes the steps of dissolving a neutron absorbing compound including a halogen and a neutron absorbing element in a molten salt coolant. The first method also includes reducing a neutron absorbing compound to a salt of said halogen and an insoluble species comprising said neutron absorbing element, said halogen being fluorine or chlorine, wherein said insoluble species undergoes fission in said molten salt Non-volatile at the temperature of the molten salt coolant during operation of the reactor. In a second approach, the one or more neutron-absorbing compounds are selected such that the one or more neutron-absorbing compounds compensate for a decrease in neutron-absorbing capacity due to absorbing neutrons in the core The resistance is reduced to control the fission rate of the core. The invention also provides a device for implementing the method.

The invention belongs to the field of cladding designs of a fusion and fission hybrid reactor, and particularly relates to a Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and an operation method thereof. The Th-U self-sustaining circulating full fused salt fuel hybrid reactor system is characterized in that a fast fission breeder reactor provides an initial easily fission fuel required by starting of a thermal fission reactor, a cladding design of the thermal fission reactor utilizes an arrangement strategy of a seed-cladding to improve the entirety neutron economy of the system, and the purposes of a high energy enlargement factor of the system, tritium breeding and thorium-uranium self-sustaining circulating of the system are realized; <233>U is loaded in an energy generating region, so that the energy generating region has a good neutronics property and is mainly used for realizing the purposes of energy amplification of the system, neutron multiplication and most <233>U breeding of the system; superfluous neutrons enter a tritium producing region and are used for tritium breeding and part of <233>U breeding of the system. According to the hybrid reactor, due to self-sustaining circulating of thorium and uranium, a thorium fuel is converted into <233>U and is gradually burn up in an operation process, and the Th-U self-sustaining circulating full fused salt fuel hybrid reactor system can effectively and stably operate for a long time just by gradually adding the thorium fuel and removing the generated fission product.