328results about "Nuclear power plant details" patented technology

A method for mitigating stress corrosion cracking in high temperature water includes introducing catalytic nanoparticles and dielectric nanoparticles to the high temperature water in an amount effective to reduce a electrochemical corrosion potential of the high temperature water.

A filter for filtering solid particles from liquids, especially for use in steam condensers and heat exchanger in thermal and nuclear power plants, said filter comprising a housing (4), a screen basket (2) located within said housing (4), a debris discharge pipe (1) for discharging accumulated and captured debris; a debris extractor arm (3) with a curvature towards the screen extending outwards at a predetermined radius with respective vertical plane, the said debris extractor arm (3) being rotatably driven over the entire length of the screen to create a low pressure between the debris extractor arm (3) and the screen (4) for complete extraction of debris and conveying to said debris discharge pipe (1).

A containment structure contains an interior volume, and a nuclear reactor is disposed in the interior volume. An ultimate heat sink pool is disposed outside of the containment structure. A condenser includes a plurality of closed-path heat pipes or closed-path thermosiphons having first ends and opposite second ends. The closed-path heat pipes or closed-path thermosiphons are embedded in the containment structure with the first ends protruding into the interior volume and the second ends protruding outside of the containment structure.

The invention relates to an inexpensively- / easily-decommissionable nuclear power plant, where a nuclear isle of one or more nuclear power-stations is installed in caverns, and further, side by side with them, a centre for characterising, treating and conditioning radioactive wastes and two repositories are installed in suitable caverns, with a final repository being adapted to store low-intermediate level nuclear wastes and a temporary repository being adapted to store spent fuel, high-level long-life radioactive materials and, in case, spare nuclear rods for reactor refueling.

A method and system are provided for propelling an aerodynamic vehicle into space. The aerodynamic vehicle uses a nuclear-based thermal rocket (NTR) propulsion system capable of producing a hydrogen exhaust. A flow of air is introduced into the hydrogen exhaust to augment the thrust force at speeds of the vehicle up to approximately Mach 6. When the speed of the vehicle is approximately Mach 6 and the altitude of the vehicle is approximately 40 kilometers, the flow of air is stopped and the vehicle is propelled into space using only the NTR.

A photocatalytic substance having the properties of an n-type semiconductor is deposited on a surface of a metal base made of a stainless steel or Inconel. When necessary, the hydrogen concentration of the reactor water is increased. A current produced by the photocatalytic substance when the same is irradiated with light or radioactive rays in a nuclear reactor flows through the metal base to reduce corrosion current. When necessary, the photocatalytic substance is provided on its surface with at least one of Pt, Rh, Ru and Pd.

The invention relates to a semi-submerged small-waterplane-area mobile platform type marine nuclear power station belonging to the technical field of offshore engineering equipment and comprising a deck, small-waterplane-area upright posts, bottom hull shells, strut rails, an anchor chain, a nuclear generating device peripheral watch box, an electric power pylon, a revolving ring, an anchor, a nuclear reactor and a converting station, wherein one ends of the eight small-waterplane-area upright posts are respectively arranged on the two bottom hull shells, and the other ends are fixedly connected with the bottom surface of the deck; both ends of the four strut rails are respectively fixedly connected with the side surfaces of the two bottom hull shells; and the nuclear generating device is arranged on the deck. The marine nuclear power station can be fixed in a certain sea area for long-term work and can also be towed by a tugboat to arbitrarily move to change the workplace. The invention has high generating capacity, long service life, high safety, fuel saving, small resistance in towing and high stability, and can endure severe sea conditions. The invention has important scientific research value, important industrial application prospect as well as military and national defense values and obvious economic benefits and social benefits.

The invention is a turbojet propulsion system which includes a compressor section, a turbine section coupled by a shaft to the compressor section, a combustion section mounted between the compressor section and the turbine section, and an exhaust duct coupled to the aft end of said turbine section. A fuel delivery system is incorporated for supplying fuel to the combustion section. A laser assembly provides electromagnetic radiation to the combustion section. An electrical generator coupled to the turbine driven shaft powers the laser assembly.

Ceramic materials that are highly resistant to strong acids such as concentrated sulfuric acid and halides such as hydrogen iodide are employed to make block elements through which a large number of circular ingress channels extend in perpendicular directions and which are joined and piled in the heat exchanging medium section to provide a compact heat exchanger that excels not only in corrosion resistance but also in high-temperature strength.

An electrical power system for a nuclear power facility includes an active alternating current (AC) power bus configured to be electrically coupled to a plurality of engineered safety feature (ESF) loads of a plurality of nuclear power systems, each of the ESF loads configured to fail to a safe position upon loss of primary AC power; a critical battery system electrically coupled to the active AC bus, the critical battery system comprising a plurality of valve regulated lead acid (VRLA) batteries; and a primary AC power source electrically coupled to the active AC bus.

A loose parts collection weir that is a nearly cylindrical structure that is integrally attached to the lower deck plate or sludge collector top plate of a steam generator to retain loose parts along the feedwater and recirculation water transit path to the tube bundle. The weir is a near vertical structure built into the upper drum of the steam generator, near the periphery of the lower deck plate or sludge collector top plate in the vicinity of the downcomer annulus. The weir may contain a radially inwardly projecting lip which forms a pocket for loose parts to collect. As the feedwater flows toward the downcomer annulus, loose parts will tend to deposit onto the lower deck plate aided by gravity and be trapped by the loose parts collection weir.

A floating nuclear power reactor includes a self-cooling containment structure and an emergency heat exchange system. The containment structure of the reactor may be flooded upon the temperature or pressure in the containment structure reaching a certain level. The reactor vessel may also be flooded upon the temperature or pressure in the reactor vessel reaching a predetermined level. The reactor includes a heat exchange system and a filtered containment venting system.