46results about How to "Improve natural circulation" patented technology

The invention relates to a passive waste heat removal system for a floating nuclear power plant. The system consists of a reactor pressure vessel 1, a passive waste heat removal heat exchanger 8 and a passive emergency cooling water tank 11, wherein the passive waste heat removal heat exchanger 8 is arranged in the emergency cooling water tank 11; an inlet/outlet of the heat exchanger is connected with a loop main coolant pipeline; the emergency cooling water tank 11 is arranged in the pressure vessel; the bottom of the water tank is connected with an ocean through a seawater pipeline; a water level in the water tank is kept consistent with the sea level, and the passive waste heat removal heat exchanger 8 is completely submerged. The passive waste heat removal system is operated under accident conditions, and heat in a loop is finally taken into an atmospheric environment by means of evaporation of water in the water tank. When the water level in the water tank is reduced, seawater automatically enters the water tank through a seawater pipeline, the water level in the water tank is kept, and the reactor is cooled for a long time.

The invention discloses a cooling water tank for a passive containment cooling system. The cooling water tank comprises a state monitoring and water supplementing system and a closed box body arrangedon the outer side of a reactor containment wall body capable of realizing automatic heat management, wherein the state monitoring and water supplementing system is used for monitoring the state of cooling water in the closed box body and supplementing water according to the state; the closed box body is connected to a heat exchanger arranged on the inner side of the reactor containment wall bodythrough a circular pipeline; the closed box body is divided into at least two water body units through a water body partition plate, and the water body units are connected to an overflow outlet and anincoming flow inlet; and the effluent circular pipeline of the closed box body and the return circular pipeline of the closed box body are separately connected to the two different water body units.The cooling water tank provided by the invention has the beneficial effects that cooling return water is layered for heat management through the water body units, and a low-temperature cooling water source can be provided to the system put into operation all the way, so that the system can obtain a relatively high natural circulating ability and heat exhaust power.

The invention discloses an accelerator driven lead bismuth cooling subcritical traveling wave reactor. The accelerator driven lead bismuth cooling subcritical traveling wave reactor comprises a mobile neutron source target, a reactor core fuel, a reactor inner component, main heat exchangers, a reactor top cover, a reactor container and a main pump. An external source neutron is provided via the mobile neutron source target; the reactor is started and ignited; the traveling wave type reactor is driven to run under the subcritical state, and a combustion wave and a proliferation wave are continued; meanwhile, the heat of the reactor core is taken out by a lead bismuth cooling agent with good chemical inertness so as to guarantee the safety of the reactor, so that the requirement for high-enrichment-degree fissile nuclear fuels for realizing critical start by the critical traveling wave reactor is prevented, the requirements for reactor core materials and high fuel consumption by the traveling of the proliferation wave are lowered, and the practical feasibility, reliability and safety of the traveling wave reactor are improved effectively.

The invention discloses an in-pile heat separation system of a liquid heavy metal cooling natural circulating pool type reactor. The system consists of an inner layer coolant inlet, an outer layer coolant inlet, a coolant inlet baffle, an inner layer heat partition plate, a middle layer heat partition plate, an outer layer heat partition plate, an inner layer coolant outlet, an outer layer coolant outlet, an inner layer coolant outlet baffle and an outer layer coolant outlet baffle. Gaps between the heat partition plates of the system are filled with liquid heavy metal and are communicated with a cold pool; coolants in the gaps between the heat partition plates are used for cooling the heat partition plates from bottom to top under the action of natural circulating driving force and are gathered into a hot pool through the coolant outlets above the heat partition plates. The in-pile heat separation system realizes a function of separating the cold pool from the hot pool in the liquid heavy metal cooling natural circulating pool type reactor; with the adoption of the complete passive design, the system is simple in structure; during running, an in-pile structural member does not need to be added or started; the heat efficiency of the liquid heavy metal cooling natural circulating pool type reactor can be effectively improved, the circulating stability of the coolants of the reactor can be guaranteed, and the economical property and the safety of the reactor can be improved.

The invention discloses a major loop circulation device used for a nuclear energy system. The device comprises a container, a core, heat exchangers, a main pump, heat separator plates, a grid plate collecting box and a pipeline; the heat separator plate divide the inner chamber of the container into an external heat tank and an external cold tank, every heat separator plate is a hollow structure, every heat separator plate is provided with a heat separator plate inlet end and a heat separator plate outlet end, the heat separator plate inlet ends are arranged at the cold tank side of the lower portions of the heat separator plates, and the heat separator plate outlet ends are arranged at the cold tank side of the upper portions of the heat separator plates. The device enhances the flow of a coolant in the cold tank, and provides a cold tank and heat tank separation function under normal running and accidental conditions of a reactor; and the device inhibits heat layering in the heat tank under a shutdown condition of the reactor, enhances the natural circulation ability of the reactor, and effectively improves the economy, the reliability and the safety of the reactor.

Present invention relates to a heat exchanging apparatus, especially an all natural circulation atmospheric cooling tower used for normal pressure nuclear heat supply pile. Said all natural circulation atmospheric cooling tower includes tower body, heat transfer pipe, chimney, normal pressure pile secondary loop heat tube, rising pipe, expansion box, water tank, thermal insulation blanket and fins. Said structure characteristics effectively enlarge waterside natural circulation ability and air side reasonable natural circulation ability for ensuring transferring heat quantity to atmosphere for long time.

The invention discloses an auxiliary heating system in a liquid state heavy metal cooling natural circulating pool type reactor. The system comprises a gas storing tank, a filter, a gas heater, a fan, a gas input tube, an inner-layer thermal insulation plate, an outer-layer thermal insulation plate, a bottom heating ring, a gas output tube, a reactor core coolant entrance baffle, a pipeline fixing steel plate, and pipelines and valves connected between the devices. The system realizes the function of assisting in heating liquid state metal in a main vessel of the liquid state metal cooling pool type reactor, has a simple structure, is convenient to start, can build large-space natural circulation of the liquid state heavy metal in the main vessel even if the reactor is at low power or in shutdown condition after being put into operation, guarantees the temperature of the liquid state heavy metal to be above the melting point, and effectively improves the reliability and safety of the reactor.

The invention belongs to the technical field of nuclear reactors, and particularly relates to a two-phase natural circulation integrated reactor which comprises a pressure vessel (1), a hanging basket(3) in the pressure vessel (1), a reactor core (2) located in the bottom of the hanging basket (3), and a heat exchange area (5) located on the periphery of the top of the hanging basket (3) and communicated with a secondary loop, and the space, located above the reactor core (2), in the hanging basket (3) is a primary loop reactor core outlet chamber (7). First steam generated by the reactor core (2) enters the heat exchange area (5) through the primary loop reactor core outlet cavity (7) to heat cooling water provided by the second loop into second steam, then the second steam is convertedinto condensate water and flows back to the reactor core (2), and the second steam is conveyed to the second loop. The reactor and the steam generator are integrated in the pressure vessel 1, equipment is simplified, the design of a main pump, a primary loop pipeline, a pressure stabilizer and the like is canceled, the risks of active equipment faults and crevasse are reduced, and the influence ofradioactive products on secondary loop equipment is avoided.

The invention relates to a preparation method of a bioavailable mineral ion chelate artificial mineral solution. On a land or in a water area where minerals which are essential to growth of animals and plants are insufficient, mineral-containing iron steel mineral slag and an ion chelate undergo ion chelation in a water solution so as to form the bioavailable mineral ion chelate artificial mineral solution; and pH value of the bioavailable mineral ion chelate artificial mineral solution is controlled to below 9. The invention has the following beneficial effect: the product is used for improving the natural circulation function on a land or in a water area where minerals which are essential to animals, plants and microbes are insufficient.

The invention discloses a novel nature cycle cooling lead-based fast reactor. The novel nature cycle cooling lead-based fast reactor at least includes: a core, a main container, a core shroud, a heatpool, a cool pool, a main heat exchanger and a reactor top cover. The main container is a circular column metal container, the two ends of the main container are sealed; the core shroud is arranged inthe main container, the inner space of the main container is divided into the heat pool and cool pool; at least one part of the core shroud has a circular column metal plate with a taper curved surface, the core is arranged at the bottom of the heat pool of the main container, the height difference is existed between the core and the main heat exchanger, the main heat exchanger is connected withthe heat pool and cool pool, and the nature circulation canal of the cooling agent is formed by the main heat exchanger, cool pool and heat pool. The nature cycle capability of the first loop coolingagent can be enhanced, and the security and economy of the nature cycle cooling lead-based fast reactor are effectively improved.

The invention provides a steam generator for metal fast reactor. The steam generator comprises a container body and a heat exchanger arranged in the container body. The container body is provided witha primary side outlet, a primary side inlet, a secondary side outlet and a secondary side inlet from bottom to top, and at least a shell pass and a first pipe pass are formed in the container body. Ahigh-temperature medium enters the shell pass through the primary side inlet, and is exported from the primary side outlet after cooling. A low-temperature medium enters the first pipe pass through the secondary side inlet, and is exported from the secondary side outlet after heating. According to the steam generator for the metal fast reactor, the mode that the high-temperature medium flows through the shell pass and the low-temperature medium flows through the pipe pass is used, the velocity of the shell pass as well as the abrasion degree of the pipe wall of a heat exchange pipe and the container wall are reduced, the circulation ability is improved, and the reliability and safety of the steam generator are improved.

The invention provides a steam generator for a metal fast reactor. The steam generator for the metal fast reactor comprises a container body and a U-shaped heat exchange pipe arranged in the containerbody. A shell pass and a pipe pass are formed in the container body. A secondary side outlet and a primary side inlet are arranged from bottom to top on one side of the container body. A secondary side inlet and a primary side outlet are arranged from bottom to top on an opposite side. A high-temperature medium enters the shell pass through the primary side inlet and is exported through the primary side outlet after being cooled. A low-temperature medium enters the pipe pass through the secondary side inlet and is exported from the secondary side outlet after being heated. Furthermore, the pipe wall of the heat exchange pipe is manufactured by adoption of lamination of multiple layers of pipe walls; each pipe wall is made by adoption of stainless steel and nickel base alloy; on the basisthat safety and reliability needed by the steam generator are guaranteed, manufacturing cost and manufacturing difficulty of the steam generator are lowered; and the integral economy of the steam generator is improved.

The invention belongs to the technical field of nuclear power plant reactor safety systems, and particularly relates to a passive steel containment heat export system, which is characterized in that a cooling cover (7) is arranged on the side wall of a containment (1) of a reactor and forms a closed annular cavity (5) with the containment (1), a cooling water loop is arranged on the cooling cover (7), the cooling water loop can inject cooling water into the annular cavity (5) from the bottom of the cooling cover (7) in a passive mode, the cooling water absorbing heat in the annular cavity (5) can flow back into the cooling water loop from the top of the cooling cover (7) in a passive mode, and the containment (1) is made of stainless steel. According to the invention, dependence of a traditional active safety system on a safety-level power supply is eliminated, high natural circulation capacity and heat removal capacity are achieved, and the capacity of relieving accident consequences for a long time without intervention after an accident is provided.