32results about How to "Increase Conversion Ratio" patented technology

The invention provides a manufacturing method of a titanium-alloy golf club head. Problems of low transforming proportion between casting materials and casting objects and low yield rate of casting objects in the former casting methods are solved. The manufacturing method includes steps that a shell mold is positioned on a rotation platform and comprises a crucible part and a mold cavity part, wherein the crucible part is communicated with the mold cavity part; the rotation platform is connected to a rotation shaft; solid titanium-alloy casting materials are placed on the crucible part of the shell mold and are heated and fused into liquid titanium alloy in 35-45 seconds in a vacuum environment; the rotation shaft is driven to drive the rotation platform to rotate; the rotation speed of the rotation shaft is 500-800 rpm; the rotation speed of the rotation shaft is accelerated from 0-0.5s to 800-1400 rpm / sec, so the liquid titanium alloy is allowed to flow into the mold cavity part of the shell mold; the rotation speed of the rotation shaft is reduced until the rotation shaft stops, and then a casted shell mold is taken down; the shell mold is damaged, so a casting object comprising a casting piece part is obtained; and the casting piece part is separated from the casting object, so at least one titanium-alloy golf club head is obtained.

The invention relates to a nuclear fuel pellet and a manufacturing method thereof, and a nuclear reactor. The nuclear fuel pellet at least comprises a first fuel zone and a second fuel zone which are arranged from inside to outside, wherein the thickness of the second fuel zone is much smaller than that of the first fuel zone; and the reactivity of a nuclear fuel material of the first fuel zone is higher than that of a nuclear fuel material of the second fuel zone. The nuclear fuel material with lower reactivity is arranged on the periphery of the nuclear fuel pellet with higher reactivity to perform the function of lowering initial reactivity margin, so that burnable poisons and / or boric acid in the reactor core are correspondingly reduced, thereby being beneficial to reactor core nuclear design and reactivity control; or more fissionable materials can be loaded to implement longer fuel cycle. More neutrons can be effectively absorbed, thereby enhancing the conversion ratio of the fuel. Besides, the nuclear fuel material with lower reactivity is arranged at the innermost ring of the nuclear fuel pellet to have the function of reducing fissible material residues, thereby enhancing the utilization ratio of nuclear fuels.

The invention discloses a production process of a thin-gauge 700MPa-grade ultra-high strength hot rolled black leather steel strip. The production process includes processes of rough rolling, finish rolling, cooling and coiling; in the process of finish rolling, the finish rolling entry temperature is 1030-1100 DEG C, and the finishing rolling temperature is 830-880 DEG C; in the cooling process,the steel strip is rapidly cooled to 750-790 DEG C through laminar flow cooling, cooled by intermediate air cooling, and then rapidly cooled to coiling temperature through the laminar flow cooling; and in the coiling process, the coiling temperature is 600-650 DEG C. The elongation of the hot rolled black leather steel strip obtained by the production process is not less than 22%; the product of strength and elongation is not less than 16 GMPa%; the steel strip has better cold forming performance and is suitable for producing cold roll forming hollow steel sections such as passenger car skeletons, truck side beams, and through beams; mechanical properties and coating surface quality requirements are met under the condition of omitting the processes of pickling chemical rust removal and mechanical rust removal; and the hot rolled black leather steel strip obtained by the production process is used to replace the Q345B, and can reduce the thickness of required steel plates, the weight ofa whole vehicle and the fuel consumption of the vehicle while the strength of a vehicle body is increased.

The invention discloses a liquid metal cooling reactor and a management method based on improving the fuel utilization rate. The reactor core is surrounded by a low-temperature strong moderator component, and a high-temperature strong moderator component is arranged on the sub-periphery. Rod assemblies and high power moderated assemblies. According to the inherent neutronic characteristics, power and burnup distribution characteristics of the liquid metal cooled fast reactor, the present invention constructs components with different functions and uses: low-power fuel components for reducing neutron leakage at the outermost periphery of the reactor core, and for reactors The high-power fuel assembly and control rod assembly inside the core form a unique liquid metal-cooled fast reactor core loading scheme, which significantly improves the average unloading fuel consumption and nuclear fuel conversion ratio of the liquid metal-cooled fast reactor, and enhances liquid metal cooling. Engineering feasibility of a fast reactor closed uranium-plutonium fuel cycle system.

The invention belongs to the field of pulse power generation, particularly relates to a pulse power supply system based on a generator cluster and an energy storage microgrid and a discharging method,and aims to solve the problem that residual energy of a pulse generator cannot be fully utilized in the prior art. The method comprises the following steps: respectively discharging each pulse generator based on a system discharge signal and parameters; grouping the pulse generators, and transferring the residual energy of each group to any pulse generator in the group; discharging again, grouping the pulse generators with available residual energy, and performing energy transfer again; and iteratively discharging the pulse generator set until the rotating speed of the pulse generator is reduced to the condition that discharge and the power generation indexes do not meet the requirements. According to the invention, by utilizing the characteristic that through the controllable rectification of charging motor, constant-voltage power generation can be carried out in a wide rotating speed range, so residual energy can be transferred in the pulse generator cluster, the conversion ratio from inertia kinetic energy to pulse electric energy is improved from the system level, and the energy utilization rate is improved.

The invention relates to a nuclear fuel pellet which comprises nuclear fuel materials. The nuclear fuel pellet at least comprises a first fuel zone and a second fuel zone which are arranged from inside to outside, wherein the reactivity of the nuclear fuel material of the first fuel zone is lower than that of the nuclear fuel material of the second fuel zone. The nuclear fuel with lower reactivity is arranged at the center of the nuclear fuel pellet, thereby avoiding the problem of low nuclear fuel material utilization ratio in the central zone, having the action of reducing fissible material residues in the discharge fuel, and avoiding the waste of the nuclear fuel materials.

The application discloses a control circuit and a switching converter using the same. The technical solutions of the embodiments of the present invention can dynamically adjust the cut-off time of the switching cycle in response to changes in output power to change the length of the switching cycle, so that when the conversion ratio is large or small, the operating frequency of the switch is automatically reduced to widen the conversion ratio range, enabling switching converters to achieve wide input voltage and wide output voltage adaptive applications.