13results about "Plant pumping arrangements" patented technology

The present application relates to nuclear power technology field, provide a kind of steam seal air extraction system, comprising: steam turbine unit, refrigeration subsystem and absorber, steam turbine unit has steam seal cavity in two ends;Absorber is connected with refrigeration subsystem to form circulation loop, absorber is connected with air extraction pipe and exhaust pipe, air extraction pipe is used to suck air and water vapor in steam seal cavity into absorber, lithium bromide solution is provided in absorber, and lithium bromide solution is used to absorb water vapor.The steam seal air extraction system described above can suck air and water vapor leaked in steam seal cavity of steam turbine unit into absorber, and water vapor is absorbed by absorber, realizes refrigeration and air extraction simultaneously, meets the air extraction demand of steam turbine unit, also takes into account refrigeration demand, eliminates the problem of system complex, numerous equipment, high auxiliary energy consumption and large volume, weight caused by air extractor and refrigeration unit independent operation, realizes the simplification of power conversion device overall composition and operation efficiency improvement.

The invention discloses a temporary ventilation system arranged in a steel containment vessel, which is suitable for the steel containment vessel and comprises an upper exhaust system, a lower exhaust system, a first transverse and vertical main pipe assembly and a second transverse and vertical main pipe assembly, and the upper exhaust system and the lower exhaust system are both arranged in the steel containment vessel. The upper exhaust system is arranged at the upper end of the lower exhaust system, one end of the first transverse and vertical main pipe assembly extends into the steel containment and is connected with the upper exhaust system, and one end of the second transverse and vertical main pipe assembly extends into the steel containment and is connected with the second transverse and vertical pipe assembly. Through the application of the invention, the temporary ventilation system arranged in the steel containment vessel is provided, and the temporary ventilation system can effectively collect flue gas generated at different heights, so that the sedimentation and residual rate of the flue gas in the steel containment vessel can be reduced; in addition, the probability that the temporary ventilation item occupies the space of the formal item is reduced, more sufficient space is provided for construction of the formal item, and the space utilization rate of the steel containment is increased.

The invention relates to the technical field of nuclear power, and discloses a modular nuclear energy small reactor efficient combined heat and power generation heating system which is characterized in that a modular nuclear energy small reactor supplies steam to a steam turbine high-pressure cylinder through a once-through steam generator, and exhaust steam enters a reheater after passing through a steam-water separator. An outlet of the reheater forms three parallel branches, the first branch is a heating steam extraction pipeline, the second branch is a low-pressure cylinder cooling steam pipeline, and the third branch is a low-pressure cylinder steam inlet pipeline. And the heat supply network heater and the secondary network water-water heat exchanger are subjected to medium isolation, and generated drain water is sent back to the deaerator through a heat supply network drain pump and is merged into the heat regeneration system. The control device adjusts the opening degree of the heating steam extraction adjusting valve and the rotating speed of the first-level network heat supply network circulating water pump and limits the upper opening degree limit of the heating steam extraction adjusting valve and the lower opening degree limit of the low-pressure cylinder cooling steam adjusting valve. High-proportion steam extraction of the reheat steam is achieved, the water supply temperature of the user side and the pressure difference of the two networks are stabilized, cold source losses are reduced, and the disturbance resistance of heat supply operation is enhanced.

The present application relates to a kind of nuclear power plant airborne radioactive containment ventilation device and group control method, process function piece includes fresh air treatment function piece, air supply and exhaust and negative pressure regulation function piece and purification function piece, fresh air treatment function piece, air supply and exhaust and negative pressure regulation function piece and purification function piece are sequentially connected by pipeline, control piece includes global group control module, fresh air treatment group control module, air supply and exhaust and negative pressure regulation group control module, purification group control module.The nuclear power plant airborne radioactive containment ventilation device and group control method of the present application can make operator only need to send a small amount of simple control instruction by global group control module, realize the function control of each component, realize the automatic operation regulation of ventilation system under different conditions, system one-key start-stop function, can greatly improve the automation level of ventilation system, reduce operator operation load, reduce human error risk, simplify ventilation system control design.

The invention relates to the technical field of reactor waste heat removal, in particular to a heat dissipation system and method for an ocean floating nuclear energy platform reactor, and the heat dissipation system comprises a loop subsystem, a natural circulation loop, a steam power generation subsystem and an ocean hot trap; the first loop subsystem comprises a reactor core, a pressure container and a coolant pipeline; the natural circulation loop comprises an intermediate heat exchanger, a seawater circulation pipeline and a waste heat discharge main pipeline, and the intermediate heat exchanger is connected with the loop subsystem through a coolant pipeline and used for discharging waste heat to the outside through natural circulation; the ocean heat trap takes external seawater as a final heat trap and is connected with a seawater circulating pipeline, a residual heat discharge main pipeline and a steam power generation subsystem; through the dual design of vapor-liquid separation and pressurization backflow prevention, the core condition for generating a condensation water hammer is avoided from the source, pipeline burst is effectively prevented, and the operation safety of the reactor heat dissipation system of the marine floating nuclear energy platform is remarkably improved.

A steam generator for a nuclear power plant is provided. The steam generator has an upright, elongated body and a tension member that extends from a proximal end, which is mounted at each mounting position on the elongated body, to a distal end, which is configured to be mounted at each load-bearing mounting position within the nuclear power plant. Each proximal end is lower than its respective distal end. When in use, the tension member receives a tensile load from the steam generator and transmits substantially all of the weight of the steam generator to the load-bearing mounting positions within the nuclear power plant.

The invention provides a multi-state sensing self-adaptive water filling method for a primary loop of a reactor, and relates to the technical field of reactor cooling, and the method comprises the following steps: collecting water flow related characteristic data in the primary loop; calculating an overall change value of the water flow; collecting data of temperature and water level in the reactor, and comparing the collected data with the initial temperature and water level of the reactor before the time T; comparing the total change value of the water flow velocity, the water flow rate, the water flow temperature and the water flow pressure with the total change coefficient of the reactor; through continuous contrastive analysis, how the temperature and the water level of the reactor are influenced by changes of various data of water flow in the loop can be quantified. The disturbance source is judged through a dynamic comparison mechanism of the total change value of the water flow and the total change value of the reactor, and meanwhile, the system can dynamically switch the control modes according to the comparison result and can adaptively adjust parameters, so that the water filling adjustment is quicker and more accurate.

The invention relates to the technical field of thermal hydraulic control of a nuclear power plant, and discloses a starting water supply system applied to a modular high-temperature gas cooled reactor nuclear power plant, which comprises a starting water supply deaerator, a starting water supply pump, a water supply pipe network assembly and a distributed control system. The water supply pipe network is physically connected to the downstream of the main feed pump outlet isolation valve. The control system adjusts the deaerator to heat steam and replenish water based on the energy balance principle, so that the feed water temperature tracks the dynamic set value in real time; thermal shock protection logic is integrated, water inlet temperature difference and temperature change rate are limited, and thermal stress damage of equipment is prevented; undisturbed switching logic based on flow conservation and cross amplitude limiting is adopted, and the total flow is maintained to be constant through double-valve cooperative adjustment when switching from starting water supply to main water supply. The problem of feed water temperature matching under asymmetric operation of a multi-module unit is solved, stable switching of water supply modes is achieved, and the standby water supply function under the working condition that main water supply is lost is achieved.

The invention relates to the technical field of high-temperature gas cooled reactors, and discloses a high-temperature gas cooled reactor primary loop atmosphere switching device and a high-temperature gas cooled reactor primary loop atmosphere switching method. The pressure relief system is connected with the pressure reduction adjusting system; the vacuumizing system is detachably connected with the pressure relief system; the pressurization adjusting system is connected with a primary loop of the reactor; and the depressurization adjusting system, the pressure relief system, the vacuumizing system and the pressurization adjusting system jointly realize atmosphere switching, pressurization and depressurization operations of the primary loop of the reactor. According to the invention, a temporary interface does not need to be additionally arranged on the primary loop of the existing reactor, and the boundary of the primary loop of the reactor does not need to be opened during atmosphere switching, so that suffocation risks and radiation risks caused by leakage of micro-positive pressure helium can be avoided, and the sealing uncertainty caused by repeated disassembly and assembly of the boundary of the primary loop is reduced; the operation convenience and the operation efficiency are improved, and rework and industrial potential safety hazards caused by leakage are reduced.

A canned rotodynamic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor. The stator windings are formed by one or more electrically conductive solid bars (12).

The invention provides an intelligent water filling and draining and volume control system for a primary loop of a nuclear reactor, which comprises a main pipeline, a compensation tank is mounted on the upper side of the main pipeline, a screw rod is rotatably matched with the inner wall of the compensation tank, a threaded sleeve is in threaded fit with the lower end of the screw rod, and a piston head is fixedly connected to the lower end of the threaded sleeve. And a driving mechanism is arranged on the upper side of the compensation tank. A lead screw driven by a servo motor and a threaded sleeve transmission structure are arranged, coordinated regulation and control are matched with a water filling and draining regulating valve, and a pawl-ratchet wheel locking mechanism and a double-unlocking design are combined, so that the volume of a loop is rapidly and accurately compensated, the pressure fluctuation problem caused by sudden volume change is reduced, mechanical locking takes effect automatically during power failure to prevent cooling liquid from flowing backwards, and the service life of the loop is prolonged. The manual unlocking mechanism and the lead screw are designed in a separated mode to guarantee emergency operation reliability, the sealing guide structure and the isolated locking component are installed in a matched mode, the operation safety and stability of the system are improved, and the requirements of the nuclear reactor for the severe working condition are met.

The utility model belongs to the technical field of nuclear industry, and particularly relates to a nuclear main pump motor and a liquid level detection device for lubricating oil of a bearing chamber of the nuclear main pump motor, the liquid level detection device comprises a shell and a liquid level detection assembly, the shell is provided with a containing cavity, and the inner side wall, facing the containing cavity, of the shell is provided with a shielding part; the liquid level monitoring module of the liquid level detection assembly is installed in the containing cavity, and the shielding part surrounds the containing cavity, so that the shielding part can effectively prevent external nuclear radiation from entering the containing cavity, the influence of the nuclear radiation on electronic components such as the liquid level monitoring module is reduced, and normal work of the liquid level detection device is ensured; according to the liquid level detection device, the liquid level measurement precision of the liquid level monitoring module and the accuracy of liquid level information signal transmission are improved, meanwhile, the risk that the structure of the liquid level monitoring module is damaged by nuclear radiation can be reduced through the arrangement of the shielding part, the maintenance frequency of the liquid level monitoring module is reduced, the service life of the liquid level monitoring module is prolonged, and therefore the practicability of the liquid level detection device is overall improved.

The disclosure relates to a device and a method for determining data representing the risk of a pumping station clogging event at an industrial site, which includes the following steps: obtaining (S01) at least one time series Q of current environmental conditions (DRCEQ); determining (S02), within historical data in the form of at least one past time series X of environmental conditions (DRCEX), a correspondence between a variable in time series Q and a variable in said at least one time series X; when at least a partial correspondence is determined, obtaining (S03), using a time series Y of past pumping station clogging events, the risk data for the occurrence of a pumping station clogging event. Fig. 1