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Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.

A flow calming assembly for a nuclear reactor includes a vessel and an enclosure situated in the vessel. A fluid circulates from the vessel to the enclosure at a bottom part of the vessel. The flow calming assembly includes an outer calming device with openings for fluid passage, the outer calming device includes an upper part and a lower part. The upper part includes a flared or conical collar extending between an upper end and a lower end, the lower part having a shape presenting a symmetry along a main axis, the lower part extending from the lower end of the upper part. The present disclosure also includes an associated reactor and an installing method.

[Problem] To provide a recycling system for continuously generated activated blanket modules in an exchange-type fusion reactor, enabling their processing without long-term cooling storage and allowing material circulation. [Solution] A dissolution regeneration unit 40 that melts structural materials of the blanket module 10 removed from the fusion reactor to desorb and recover tritium remaining in the structural materials while separating elements that serve as sources of long-lived radionuclides from the molten metal to form regenerated metallic materials, and a supply unit 50 that supplies the recovered tritium to the fuel system of the fusion reactor 2 and provides the regenerated metallic materials as raw materials for new modules. By designating the destination of the regenerated metallic materials for uses inside the radiation control area 4, cooling storage for clearance becomes unnecessary, and materials circulate shortly after removal. [Selected Figure] Figure 1

The present invention relates to an integrated system for irradiation, dissolution, and transfer of the irradiated target and a target holder for irradiating solid targets in a coupled particle accelerator. The integrated system is innovative for particle accelerator target holders, as it optimizes the process of producing radioisotopes from solid targets. The target holder coupled to the system combines the steps of irradiation, controlled dissolution, and efficient transfer of irradiated targets. Dissolution occurs with temperature control directly in the accelerator bunker, and the transfer of the dissolved target to a hot cell is carried out through pre-existing piping. This target holder system offers flexibility to irradiate different metals (targets) and adjust the amount of target to be irradiated according to demand, improving process efficiency and reducing operating costs and waste.

本发明涉及一种核反应堆卸压喷洒装置及核反应堆卸压系统，核反应堆卸压系统包括核反应堆卸压喷洒装置。在该核反应堆卸压喷洒装置中，通过在直线主管上设置多个主喷洒孔，并在每一弧形分管上设置多个预喷洒孔，能够有效提高高温高压的蒸汽的冷凝速率，保证核电系统的运行稳定性。其次，相比于现有技术中通过一个大缺口直接排出蒸汽的方式而言，本发明采用的是多个均匀的主喷洒孔及多个均匀分布的预喷洒孔进行蒸汽排放，从而限制蒸汽经由孔体排出后所形成的气泡大小，进而有效降低水锤冲击，提高卸压过程中的运行稳定性。

To provide a nuclear power output control system capable of advancing the combustion of core fuel as planned and efficiently utilizing the core fuel.SOLUTION: The nuclear power generation output control system 10 includes a core fuel burnup calculation unit 11 that calculates the burnup of the core fuel from the detected local reactor power, and a core fuel plan value comparison unit 12 that compares the core fuel burnup signal from the core fuel burnup calculation unit 11 with the core fuel plan value. This device is provided with a discrimination device 12 for discriminating the necessity of the adjustment of the burnup degree of the core fuel from a deviation signal from a core fuel plan value, a control rod selection part 14 for selecting a control rod 9 to be drawn/inserted when the deviation signal becomes a preset prescribed value or more, and a control rod drawing/insertion command part 15 for outputting the drawing/insertion command of the selected control rod 9 to a control rod operation monitoring device 8.SELECTED DRAWING: Figure 2

The utility model relates to a laser head attachment for the localized removal of radioactive aerosols from the laser decontamination zone of an object's surface. The technical result is the effective localized removal of radioactive waste from any surfaces, including large and stationary objects, without destroying them. The attachment is designed with an air duct for the attachment, capable of being hermetically connected to the laser head, and comprises a nozzle tip, hermetically connected thereto and positioned at an angle to the axis of the tip. Moreover, the tip is configured with a height that fixes the distance from the treated surface to the laser head, the axis of the nozzle tip coincides with the axis of propagation of laser radiation. At one end, the attachment is provided with openings for air inflow, and at the other end of the attachment, an outlet pipe is provided, communicating with the air duct of the attachment, wherein the opposite end of the outlet pipe is configured for detachable connection to an air line for aerosol aspiration. 7 c.p. fils, 14 figs.

It is proposed a method and device for the realization and reaching the required parameters for a nuclear reaction of light nucleus in liquid. The time for the plasma sustainability is achieved by excitation of long train of high peak intensity ps pulses. The preliminary estimations show a power intensity of 1019 - 1020 W/cm2 ( corresponding for the wavelength of 1064nm is round 5.1011 V/m electric field ). It is observed, that the emission of the D ions at 656nm continues after the end of the excitation and ions recombination life time, which leads to the conclusion that a high energy exothermal reaction is triggered.

本发明公开了一种无源自锁控制棒连接器，包括互锁组件和第一锁体组件；互锁组件包括固设于驱动杆一端的基座和固设于控制棒一端的第二连接座，基座和第二连接座之间设置锁紧位和第二锁体；第二锁体与第二推动件连接，第二锁体被配置为，能够被第二推动件推动进入所述锁紧位，使得基座和第二连接座互锁连接；第一锁体组件包括第一锁体和与第一锁体连接的第一推动件，第一锁体被配置为，能够被第一推动件推动进入锁紧位并使第二锁体脱离锁紧位，使得所述基座和第二连接座能够分离。本方案通过互锁组件与第一锁体组件的配合，无需额外引入动力源即可实现控制棒与驱动杆的自锁连接和分离，且不占用驱动件内部空间，具有良好的适配性。