39results about How to "Small absorption cross section" patented technology

The invention aims at providing a nuclear fuel rod with ceramic cladding and metallic pellet. The nuclear fuel rod with ceramic cladding and metallic pellet has the advantages that the heat-conducting property of the nuclear fuel rod can be improved, the central temperature of the fuel pellet is lowered or the fuel power density is effectively improved, the fuel rod cladding mechanical property, corrosion resistance and radiation resistance are greatly improved, the breakage rate of the fuel rod is lowered, the discharge burnup of the fuel rod is remarkably increased and the fuel utilization rate is greatly improved; meanwhile, the fuel rod has good neutronics performance, and can be widely used in a fast reactor or a thermal reactor. The cladding of the nuclear fuel rod provided by the invention is a SiCf / SiC composite ceramic material cladding, the metallic fuel pellet adopts a U-Zr or U-Pu-Zr alloy fuel pellet; a gap between the cladding and the fuel pellet is filled with low-melting-point metal; and a lengthened air cavity is designed at the upper part of the fuel rod.

The invention discloses a ZrC and UO2 composite fuel pellet as well as a preparation method and application of the ZrC and UO2 composite fuel pellet and aims at solving the problem that UO2 is super-low in heat conductivity to result in relatively low safety performance of a fuel assembly in the prior art. The ZrC and UO2 composite fuel pellet disclosed by the invention is prepared by sintering raw materials including UO2 and ZrC at high temperature, wherein the enrichment degree of 235U in UO2 is 1%-5%, and the dosage of ZrC does not exceed 10vol% of total quantity of UO2 and ZrC. The preparation method disclosed by the invention comprises the steps: uniformly mixing UO2, ZrC and a lubricant according to a certain proportion, carrying out high-temperature sintering, carrying out furnace cooling, then, taking out a sample, and processing the sample to the required shape and size. By using the ZrC and UO2 composite fuel pellet disclosed by the invention, the heat conductivity of UO2 canbe effectively increased, so that the safety performance of the fuel assembly is improved. The preparation method disclosed by the invention is simple and convenient to operate.

The invention discloses a preparation method of a SiC-based multi-phase ceramic solidified body used for radioactive graphite solidification treatment, and the preparation method is characterized by comprising the following steps: using silicon powder, graphite powder, MgO and Al (OH) 3 as raw materials, preparing MgAl2O4 powder, preparing Si-C powder, preparing SiC-MgAl2O4 multi-phase powder, adding polyvinyl alcohol, performing sol-granulating, shaping and glue discharging, vacuum hot-pressing sintering and the like to obtain the SiC-based multi-phase ceramic solidified body at low temperature. The SiC-based multi-phase ceramic solidified body with excellent anti-radiation stability, chemical stability, mechanical stability and thermal stability is prepared from the safe and cheap raw materials by a simple and practical vacuum hot-pressing sintering technique at the low temperature. The prepared SiC-based multi-phase ceramic solidified body is particularly suitable for the ceramic solidification treatment of high-radioactive activity graphite waste.

The invention relates to a portable neutron detection device. The device comprises an outer sleeve (2), as well as a neutron scintillator conversion screen (5), a photoconductive material (6), an end window photomultiplier (7) and a base (3) which are sequentially arranged in the outer sleeve (2) and are in compression fitting joint, wherein an output port (4) extruding at the outer end of the base (3) is formed at one end of the end window photomultiplier (7), and connected with a preamplifier (9), a main amplifier (10) and a multi-channel analyzer (11) in sequence through leads; a screwable protective cover (1) with an inner thread is arranged at the front end of the outer sleeve (2); the protective cover (1) and the outer sleeve (2) are made of an aluminum material; the screwing progress can be adjusted by rotating the protective cover (1); and a magnetic shielding material (8) is coated on the outer surface of the end window photomultiplier (7). The portable neutron detection device can effectively shield an outer optical signal, has high efficiency in neutron detection, and is simple in structure and convenient to carry.

The invention discloses a method of an electrolytic plating power supply, including a main box, a coolant, an information processor, a signal switch, a current sense port, a heat-dissipating fan, a voltage detection port, a voltage regulator, an output port, current regulate component, ventilation fin, electronic touch display, safety signal lamp, insulated handle, electrolytic cell, rectify circuit, single junction transistor oscillation trigger circuit, inverter circuit, transformer, current voltage detection circuit, load, safety power-off device and information processing device. The invention has the advantages that: the design of the electrolytic plating power supply is reasonable, the information processor facilitates the sorting and merging of the obtained data and the sending of instructions to various circuit ports, The current detection port facilitates the control and detection of the output current and voltage, the current regulating module keeps the internal current stable, and the safety signal lamp facilitates the early warning of the user and the real-time expression of the internal running state.