1663results about "Containment" patented technology

The present invention provides a coating inorganic fiber toughened MAX phase ceramic composite material and a preparation method thereof. The composite material adopts a MAX phase ceramic material as a matrix and adopts coating inorganic fibers as a toughening phase, wherein the coating inorganic fiber content is 0.5-90% (by volume), and the coating inorganic fibers are completely dispersed in the matrix and are inorganic fibers with the surface coated with the coating. Compared with the composite material in the prior art, the composite material of the present invention has the following characteristics that: the interface reaction between the inorganic fibers and the MAX phase ceramic can be effectively inhibited, the thermal expansion coefficient and elasticity modulus matching degree between the inorganic fibers and the MAX phase ceramic can be effective regulated, the effective improvement of the fracture toughness and the high temperature resistance of the MAX phase ceramic composite material can be achieved, the problems of high brittleness and insufficient use reliability of the MAX phase ceramic can be fundamentally solved, and the coating inorganic fiber toughened MAX phase ceramic composite material has potential application prospects in the high technology fields of civil use, aviation, aerospace, nuclear industry and the like, and is especially for the fission and fusion reactor nuclear power plant inner wall structure material.

A containment vessel includes a primary containment vessel containing a reactor pressure vessel, an upper secondary containment vessel arranged above the primary containment vessel, and a gas-phase vent pipe linking the primary containment vessel and the upper secondary containment vessel by way of an isolation and connection switching system. The gas-phase vent pipe may be arranged either inside or outside the primary containment vessel and the upper secondary containment vessel. Alternatively, it may be embedded in the wall. An igniter may be arranged in the upper secondary containment vessel. The air in the upper secondary containment vessel may be replaced by nitrogen. A gravity-driven flooding system pool may be arranged in the upper secondary containment vessel and cooling water may be led from the inside of the pool to the inside of the primary containment vessel.

A molten salt breeder reactor that has fuel conduit surrounded by a fertile blanket. The fuel salt conduit has an elongated core section that allows for the generation of electrical power on a scale comparable to commercially available nuclear reactors. The geometry of the fuel conduit is such that sub-critical conditions exist near the input and output of the fuel salt conduit and the fertile blanket surrounds the input and output of the fuel salt conduit, thereby minimizing neutron losses.

Provided are an underwater processing apparatus which can effectively prevent water from entering a shield for a workpiece having a surface ruggedness, and in which variation in a gas flow for a processing part is reduced, a processing method and an application thereof to a nuclear reactor, and the under water processing device is composed of a shield means which locally cover the processing part with the gas in order to prevent water from entering the shield member, the shield means having a solid wall formed of a member which is slidable in a part where it make contact with the workpiece, and adapted to make contact with the workpiece and to be moved up and down by a pressing force, and a water jetting means for forming a water curtain around the outer periphery of the solid wall.

A power module assembly includes a reactor core immersed in a coolant and a reactor vessel housing the coolant and the reactor core. An internal dry containment vessel submerged in liquid substantially surrounds the reactor vessel in a gaseous environment. During an over-pressurization event the reactor vessel is configured to release the coolant into the containment vessel and remove a decay heat of the reactor core through condensation of the coolant on an inner surface of the containment vessel.

The present application relates to microfluidic devices and related technologies, and to chemical processes using such devices. More specifically, the application discloses a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in a fast, efficient and compact manner. In particular, this application describe an automated, stand-alone, microfluidic instrument for the multi-step chemical synthesis of radiopharmaceuticals, such as probes for PET and a method of using such instruments.

A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The used syringe is sent back in the pig to the radiopharmacy for disposal. The pig includes a cap that is removably attached to a base. Shielding elements, typically formed from lead, are enclosed in the cap and the base. The pig can be used to transport a conventional syringe or a safety syringe. The pig can be used with or without an inner liner in the base. There is never an inner liner in the cap.

The present application is generally directed to microfluidic devices and methods for the achievement and assessment of chemical and radiochemical purity of (microfluidic) radio-synthesis products. More particularly, the current application relates to systems for purification and analysis of radiochemical products yielded by microfluidic synthesis devices.

Macro- and microfluidic devices and related technologies, and chemical processes using such devices. More specifically, the devices may be used for a fully automated synthesis of radioactive compounds for imaging, such as by positron emission tomography (PET), in an efficient, compact and safe to the operator manner. In particular, embodiments of the present invention relate to an automated, multi-run, microfluidic instrument for the multi-step synthesis of radiopharmaceuticals, such as PET probes, comprising a remote shielded mini-cell containing radiation-handing components.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UCl_xF_y are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.

A nuclear reactor having a penetration seal ring interposed between the reactor vessel flange and a mating flange on the reactor vessel head. Radial ports through the flange provide passage into the interior of the reactor vessel for utility conduits that can be used to convey signal cables, power cables or hydraulic lines to the components within the interior of the pressure vessel. A double o-ring seal is provided on both sides of the penetration flange and partial J-welds on the inside diameter of the flange between the flange and the utility conduits secure the pressure boundary.

In a nuclear reactor internal structure, generation and promotion of object-downstream separating vortices are suppressed so that coolant uniformly flows in a reactor core and pressure loss of flow of the coolant is reduced so that the flow of the coolant is stabilized. A lower connecting plate 30 arranged in a lower plenum 8 comprises a ring portion 31 in which an arcuate portion 32 and a cut-off portion are alternately formed. An outer peripheral portion of the ring portion 31 is asymmetric relative to a flow direction of main flow and also asymmetric relative to a separating flow generation direction.

Systems and methods are disclosed for producing customized, predictable and reproducible supplies of radioisotopes using, for example, a reactor housing that is fabricated from a radioactive shielding material and has both an internal volume and a surface that comprises an entry port and an exit port, a chromatographic column that is positioned within said internal volume such that a first end of said column is in fluid communication with said entry port and a second end of said column is in fluid communication with said exit port, and a changeable filter module that is disposed external to said reactor housing and in fluid communication with said exit port.

A light water reactor to safely convert depleted uranium into a fuel source that could be used as a sustainable source of energy for centuries. The reactor is a type of breed-burn reactor uniquely combined with a proliferation-resistant fuel cycle with no uranium enrichment and no plutonium isolation. It is comprised of a compact factory-produced fast region and a thermal region that produces about 95% of the core power and contains the passageways for transports of delayed-neutron emitters to the fast region, where they can provide additional neutrons (source-based mode) or all the necessary excitation without an external neutron source (self-regulating mode). A second embodiment of the invention is a small unit driven by a neutron source with beam recycling for propulsion, electrical power or radioisotope production. It could also serve as a demonstration facility for the transmutation reactor with fission-fusion fuel.

A combinatorial heterogeneous-homogeneous reactor configuration in which an array or groups of homogeneous fuel assemblies are interlinked together in a heterogeneous lattice. The present invention removes the limitation of a homogeneous reactor by providing a reactor concept that utilizes the inherent advantages of homogeneous fuel elements but in a heterogeneous fuel lattice arrangement that limits the power density of any one homogeneous fuel element and yet forms a reactor arrangement that is capable of producing any product demand of interest. The present invention provides a method for producing medical isotopes by the use of a modular reactor core comprised of homogeneous fuel assemblies arranged in a regular rectangular or triangular pitch lattice. The aqueous fuel solution is contained within individual fuel assemblies that are right circular cylinders clad in corrosion-resistant alloys such as stainless steel, zircalloy, zircalloy alloys, or other metal alloys that are resistant to corrosive fissile environments but preserve neutron economy. The fuel assemblies are supported below by a core plate that is tied directly to the lower reactor support structure. The bottom of each assembly opens into a common plenum area which provides a hydrodynamic communication/coupling path between the individual assemblies in the lattice. The fuel assemblies are supported above by an upper plate that is welded to each assembly tube. The top of each assembly opens to a common upper plenum which provides a means of thermodynamic pressure equalization among the four assemblies in the reactor core lattice.

A necessary size and number of modules each obtained by housing a member including heat exchanger tube panels each comprising a heat exchanger tube bundle and headers for the heat exchanger tube bundle, an upper casing of an exhaust heat recovery boiler (HRSG), provided above the heat exchanger tube panels, heat insulators, and heat exchanger tube panel support beams provided on the upper surface of the upper casing into a transportation frame, are prepared according to design specifications of the HRSG, and side casings and a bottom casing except for the ceiling part casing are constructed in advance at a construction site of the HRSG, and the modules are suspended from above between adjacent support beams of the ceiling part to dispose the heat exchanger tube panel support beams of the modules at the set heights of the ceiling part support beams, and the support beams and the ceiling part support beams are connected and fixed via connecting steel plates, whereby the respective modules are transported to the HRSG construction site and can be easily constructed.

An offshore, floating, moored, nuclear power generating plant and multi-purpose platform is disclosed herein. In a preferred embodiment, the invention consists of a spar or cell spar platform with multi-purpose, all weather topside decks, attached to a submerged “dry tank” that further includes: reactor generator deck(s), power plant main control deck, and central plant deck, that are all integrated within a watertight ballast hull. The invention design further includes cells that are modular for facilitating factory assembly and ultimate construction in a shipyard environment. Reactor vessels are typical naval nuclear reactor having a time tested outstanding safety record. A plurality of reactor generator modules are interconnected and operate independently and collectively and are transmitted by a plurality of high voltage direct current (HVDC) submarine cables through a transformer to the electrical grid. Multipurpose topside decks house vessel commend, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational advantages over the current art of power generation.

The invention discloses an experiment device for simulating retention of in-pile melts obtained by melting of a reactor core of a nuclear reactor and an experiment method. The device consists of a copper heating section, a quartz glass component and a data measurement system. According to the experiment device, a melt hard shell of the reactor core is simulated through a semispherical copper ball shell; decay heat is simulated through a spiral heating wire embedded into the semispherical shell; the inner wall surface of a lower enclosure of a pressure container is simulated through quartz glass, and therefore, a flowing heat exchange phenomenon of a narrow gap between the inner wall surface of the pressure container of the reactor and the melt hard shell can be simulated, and the influence on the retention of the in-pile melts caused by flowing of water in the narrow gap can be researched. The experiment device has the advantages of visible experiment process, high experiment precision, high safety, easiness in operation and the like. A running practice shows that the experiment device runs stably and can thoroughly meet a design requirement.

The invention relates to a containment filtering and discharging system. As a shielding plant (11) is arranged outside a containment, a discharging and filtering sub system is arranged in the shielding plant (11), a water washing filter (3) and a metal fiber filter (4) connected with each other in sequence are arranged in the discharging and filtering sub system and the water washing filter (3) is provided with a waste liquid returning pipeline (10), gases discharged by the containment are doubly filtered by the water washing filter (3) and the metal fiber filter (4), and the waste liquid accumulated in the water washing filter (3) self-flows into the containment through the waste liquid returning pipeline (10) under the effect of gravity force. Therefore, according to the invention, serious accidents occurred in pressurized-water reactor nuclear power stations are eased, overpressure failure of the containment is prevented, radioactive substances released to the environment are reduced, safeties of the surrounding environment and personnel are protected, and the safety of the nuclear power stations are greatly improved.

The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of tiie thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

The invention concerns a device for synthesis of radiopharmaceutical products based on chemical reagents contained in bottles, said device comprising several reaction compartments, transfer means between said bottles and said reaction compartments as well as mechanical means acting on said transfer means and enabling to monitor and control mechanically the transfer of chemical reagents. The invention is characterized in that it comprises: a fixed module including at least the mechanical means; a removable and disposable module, essentially in the shape of a support, whereon are arranged the transfer means between said bottles and said reaction compartments, said removable and disposable module not including any mechanical means; and means for securing said removable and disposable module to said fixed module.