Class / Patent application number | Description | Number of patent applications / Date published |
376402000 | Manipulated or used exterior of reactor core | 19 |
20090122944 | FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM - A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel. | 05-14-2009 |
20090207963 | NUCLEAR REACTOR - The present invention generally relates to a nuclear reactor, comprising a reactor core, neutron reflectors surrounding the core on all sides, uranium oxide as reactor fuel and a coolant that is liquid at proces conditions and solid at room temperature. The invention is characterized in that the nuclear reactor comprises a thermal isolation which is impermeable for the coolant, which is of a different material than the coolant and which has a melting point higher than the temperature in the reactor, in such a way that the thermal isolation is surrounding the reactor core and the neutron reflectors on all sides in order to provide a leak-tight containment function. Therefore the phenomenon is being used that the temperature on the outside of the installation is always far below the melting point of the coolant, in such a way that the coolant solidifies on the outside of the installation under all possible circumstances. The heating channels, which are preferably embedded in the reflectors, contain heating elements for heating the reactor core to a temperature higher than the melting point of the coolant before the reactor is filled with the coolant and before the start up of the reactor begins. The whole primary system of the installation may fit in a transportable container. | 08-20-2009 |
20090323886 | Methods and apparatuses for removal and transport of thermal energy - Methods and apparatuses are provided for the removal and transportation of thermal energy from a heat source to a distant complex for use in thermochemical cycles or other processes. In one embodiment, an apparatus includes a hybrid heat pipes/thermosyphon intermediate heat exchanger (HPTIHX) system that is divided into three distinct sections, namely: an evaporation chamber, a condensation chamber, and a working fluid transport section of liquid and vapor counter-current flows. | 12-31-2009 |
20110268242 | Hydrogen and Oxygen Recombination Catalyst, Recombination Apparatus, and Nuclear Plant - A recombination apparatus is provided to an off-gas system of a boiling water nuclear plant. An off-gas system pipe connected to a condenser is connected to the recombination apparatus. A catalyst layer filled with a catalyst for recombining hydrogen and oxygen is disposed in the recombination apparatus. The recombination catalyst has a percentage of the number of Pt particles whose diameters are in a range from more than 1 nm to not more than 3 nm to the numbers of Pt particles whose diameters are in a range from more than 0 nm to not more than 20 nm, falling within a range from 20 to 100%. The condenser discharges gas containing an organosilicon compound (ex. D5), hydrogen, and oxygen, which is introduced to the recombination apparatus. Use of the above recombination catalyst can improve the performance of recombining hydrogen and oxygen more than conventional catalysts and the initial performance of the catalyst can be maintained for a longer period of time. | 11-03-2011 |
20110286569 | FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM - A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel. One or more bending parts are formed on at least the pipe of primary loop coolant of the pipes, and a part of the bending part on a downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of the bending part is formed in either a planar or flat shape. | 11-24-2011 |
20120140866 | FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM - A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel. One or more bending parts are formed on at least the pipe of primary loop coolant of the pipes, and a part of the bending part on a downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of the bending part is formed in either a planar or flat shape. | 06-07-2012 |
20130259187 | CARBON DIOXIDE PRODUCTION - Apparatus for the production of carbon dioxide from limestone includes a nuclear reactor ( | 10-03-2013 |
376403000 | Including tank, pool, or reservoir (e.g., swimming pool) | 8 |
20100290579 | NUCLEAR REACTOR, IN PARTICULAR POOL-TYPE NUCLEAR REACTOR, WITH NEW-CONCEPT FUEL ELEMENTS - The present invention relates to a nuclear reactor, in particular a pool-type nuclear reactor cooled with liquid metal (for example, a heavy metal such as lead or lead-bismuth eutectic) or with sodium or molten salts, having a core formed by a bundle of fuel elements and immersed in a primary fluid circulating between the core and at least one heat exchanger; the fuel elements extend along respective parallel longitudinal axes and have respective bottom active parts immersed in the primary fluid to constitute the core, and respective service parts that extend at the top from the active parts and emerge from the primary fluid; the fuel elements are mechanically supported via respective top end heads anchored to supporting structures and can be operated via handling machines. | 11-18-2010 |
376404000 | Having reactor core and heat exchanger or pump therein | 7 |
20150325317 | NUCLEAR REACTOR - A nuclear reactor comprising a housing having disposed therein an active region that contains a bundle of rod-type fuel elements enclosed in a tubular shell and submerged in a primary coolant that circulates between the active region and at least one heat exchanger. In order to reduce the level of pressure of gaseous fission fragments accumulating below the fuel element shell and to enable the most uniform possible distribution of the velocity field of the primary coolant at the inlet to the active part of the fuel elements, said fuel elements are provided in their upper parts with active portions, which are filled with fuel, and hollow working portions, which are situated below said active portions. | 11-12-2015 |
376405000 | With particular heat exchanger structure | 6 |
20090129532 | STABLE STARTUP SYSTEM FOR A NUCLEAR REACTOR - A nuclear reactor module includes a reactor vessel containing coolant, a reactor core submerged in the coolant, and a heat exchanger configured to remove heat from the coolant. The nuclear reactor module further includes one or more heaters configured to add heat to the coolant during a startup operation and prior to the reactor core going critical. | 05-21-2009 |
20110075786 | Heat exchanger, methods therefor and a nuclear fission reactor system - A heat exchanger, methods therefor and a nuclear fission reactor system. The heat exchanger comprises a heat exchanger body defining an exit plenum chamber therein shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between the heat transfer members. The flow passages open into the exit plenum chamber. Spacing of the heat transfer members by the predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Each heat transfer member defines a flow channel therethrough for flow of a cooler secondary heat transfer fluid. Heat transfer occurs from the hot primary heat transfer fluid to the cooler secondary heat transfer fluid as the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid simultaneously flows through the flow channel. | 03-31-2011 |
20110075787 | Heat exchanger, methods therefor and a nuclear fission reactor system - A heat exchanger, methods therefor and a nuclear fission reactor system. The heat exchanger comprises a heat exchanger body defining an exit plenum chamber therein shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between the heat transfer members. The flow passages open into the exit plenum chamber. Spacing of the heat transfer members by the predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Each heat transfer member defines a flow channel therethrough for flow of a cooler secondary heat transfer fluid. Heat transfer occurs from the hot primary heat transfer fluid to the cooler secondary heat transfer fluid as the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid simultaneously flows through the flow channel | 03-31-2011 |
20110075788 | Heat exchanger, methods therefor and a nuclear fission reactor system - A heat exchanger, methods therefor and a nuclear fission reactor system. The heat exchanger comprises a heat exchanger body defining an exit plenum chamber therein shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between the heat transfer members. The flow passages open into the exit plenum chamber. Spacing of the heat transfer members by the predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Each heat transfer member defines a flow channel therethrough for flow of a cooler secondary heat transfer fluid. Heat transfer occurs from the hot primary heat transfer fluid to the cooler secondary heat transfer fluid as the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid simultaneously flows through the flow channel | 03-31-2011 |
20150310949 | WATER INTAKE INSTALLATION FOR COOLING A NUCLEAR POWER PLANT, AND NUCLEAR POWER PLANT COMPRISING SUCH AN INSTALLATION - Water intake installation to supply water to a heat exchanger cooling circuit of one or more reactor units of a nuclear power plant, and comprising a suction basin from which a pumping station sucks water. The installation further comprises a suction tunnel communicating with the suction basin to supply it with water, connected to two water intakes submerged in a body of water. A part of the suction tunnel forms a loop having two ends that communicate with the suction basin. The disclosure also relates to a method for producing such a water intake installation, as well as a nuclear power plant comprising such an installation, optionally with several reactor units supplied with water by a same suction basin. | 10-29-2015 |
20150357064 | WATER INTAKE INSTALLATION FOR COOLING A NUCLEAR POWER PLANT, AND NUCLEAR POWER PLANT COMPRISING SUCH AN INSTALLATION - Water intake installation comprising a suction basin from which a pumping station supplies water to a cooling circuit, and a suction tunnel that supplies water to the suction basin so as to maintain a sufficient water level. The water intake installation furthermore comprises a system for supplying additional water, able to supply water to the suction basin from an emergency water reserve. The system for supplying additional water comprises a water duct connecting the suction basin to said emergency water reserve and an obstructing device able to open the water duct if the water level in the suction basin drops in a way defined beforehand as being abnormal. Nuclear power plant comprising such a water intake installation, especially suitable for establishment on a coastline vulnerable to tsunami flooding. | 12-10-2015 |
376406000 | Compact or integral (e.g., heat exchanger, core, pumps in same vessel) | 2 |
20120275558 | PRESSURIZED-WATER-COOLED NUCLEAR REACTOR WITH COMPACT STEAM GENERATORS - A nuclear reactor cooled with pressurized water, having a pressurized tank installed in which are compact steam generators; each steam generator comprises a plurality of heat-exchange tubes having respective spiral portions set in levels on top of one another to form at least one annular tube bundle delimiting a substantially cylindrical internal central zone, pre-arranged for supply from above with primary water, which then traverses the tube bundle radially. | 11-01-2012 |
20140321598 | COMPACT NUCLEAR REACTOR WITH INTEGRAL STEAM GENERATOR - In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel ( | 10-30-2014 |
376407000 | With jet pumps | 2 |
20080292043 | Composite Sparger - A composite sparger for use in elevated temperature and corrosive environments. The composite sparger is formed from a thermally conductive non-combustible metal substrate. The surfaces of the conductive non-combustible metal exposed to the reactor environment are protected with a corrosion resistant layer. The corrosion resistant layer protects the substrate material from the corrosive environment of the reactor vessel and the substrate material conducts heat away from the corrosion resistant layer to prevent combustion of the corrosion resistant layer. The substrate material and corrosion resistant material may be selected so as to provide for sufficient thermal conduction to prevent combustion of the corrosion resistant material. | 11-27-2008 |
20120307958 | BOLT FIXING DEVICE OF JET PUMP BEAM - A jet pump including a riser as a coolant supply tube, an inlet mixer forming a turn-around path for the coolant, a diffuser, and a jet pump beam provided with a bolt fixing device is disclosed. The bolt fixing device includes: a head bolt of a jet pump beam for pushing and supporting the inlet mixer from an upper side of the riser, the head bolt being provided with a polygonal head portion; a lock cap provided on the polygonal head portion of the head bolt; a body housing disposed on an upper surface of the jet pump beam and adapted to accommodate the lock pin; a plurality of tapered external teeth formed on an outer peripheral side surface of the lock cap; and a plurality of internal tooth-shaped grooves formed to the body housing to fix the head bolt of the jet pump beam. | 12-06-2012 |