Patent classifications
G21C1/32
METHOD OF OBTAINING TRANSURANIC ELEMENTS AND CREATING A NANOFUEL FROM THE TRANSURANIC ELEMENTS
A method of obtaining transuranic elements for nanofuel including: receiving spent nuclear fuel (SNF); separating elements from SNF, including a stream of elements with Z>92, fissile fuel, passive agent, fertile fuel, or fission products; and providing elements. A method of using transuranic elements to create nanofuel, including: receiving, converting, and mixing the transuranic elements with a moderator to obtain nanofuel.
INTEGRAL REACTOR PRESSURE VESSEL TUBE SHEET
A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.
LIGHT-WATER NUCLEAR REACTOR (LWR), IN PARTICULAR A PRESSURISED WATER REACTOR (PWR) OR BOILING WATER REACTOR (BWR), INCORPORATING AN INTEGRAL, AUTONOMOUS, PASSIVE DECAY HEAT REMOVAL SYSTEM
An organic Rankine cycle machine and a supplementary reservoir of water, distinct from the pool, the energy stored in the pool being the hot source for the organic Rankine cycle evaporator, the supplementary reservoir of water feeding the organic Rankine cycle condenser directly via a dedicated pump to constitute the cold source of the organic Rankine cycle condenser.
LIGHT WATER NUCLEAR REACTOR (LWR), IN PARTICULAR PRESSURIZED WATER REACTOR (PWR) OR BOILING WATER REACTOR (BWR), WITH A HEAT SINK ON THE GROUND AND INCORPORATING AN AUTONOMOUS DECAY HEAT REMOVAL (DHR) SYSTEM
An ORC engine and an additional water reservoir, separate from the pool, the energy stored in the pool being the heat source for the evaporator of the ORC, the additional water reservoir directly supplying the condenser of the ORC via a dedicated pump in order to constitute the heat sink for the condenser of the ORC.
NUCLEAR REACTOR OF INTEGRAL TYPE
Claimed embodiments of the integral nuclear reactor relate to nuclear technology and can be used in reactors with different types of heat transfer fluids with a high boiling point, such as, for example, liquid metals, molten salts, etc. Design features of the invention embodiments claimed which have a coil heat exchanger sectioned along the secondary heat carrier circuit provides for an improvement in technical and economic features due to a decrease in metal consumption of the reactor; efficient use of the internal volume of the reactor; improved safety in case of the heat exchanger tube leaks; enabling the removal of residual heat during the time after removal of the protective plug before fuel discharge operations.
Nuclear reactor provided with a raised heat exchanger
A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.
Nuclear reactor provided with a raised heat exchanger
A nuclear reactor cooled by liquid metal or by molten salts, provided with a heat exchanger, having inlet of the primary fluid in the lower part and circumferential outlet window in the vicinity of the free surface of the primary fluid in the cold collector. The outlet window is located in an intermediate position with respect to the tube bundle partially raised with respect to the free surface in the cold collector and supplied with primary fluid throughout its height by means of an ancillary device for creating an underpressure in the cover gas of the exchanger with respect to the cover gas in the vessel. The raising of the exchanger and the positioning of the outlet window in the vicinity of the free surface of the primary coolant help to minimize the displacement of primary fluid in the event of accidental release of secondary fluid inside the heat exchanger.
AN INTEGRATED PASSIVE REACTOR SYSTEM
The present invention provides an integrated passive reactor system comprising a pressure vessel, a containment vessel arranged outside the pressure vessel and a reactor core arranged inside the pressure vessel, wherein the primary loop operates in full natural circulation. The integrated reactor system is also provided with a secondary side passive residual heat removal system comprising primary loop heat exchanger(s) arranged inside the pressure vessel and passive residual heat removal heat exchanger(s) arranged outside the containment vessel, wherein the primary loop heat exchanger(s) is/are arranged above the reactor core, the passive residual heat removal heat exchanger(s) is/are arranged inside water tank(s) which is/are fixed outside the containment vessel, and the primary heat exchanger(s) and the passive residual heat removal heat exchanger(s) are connected by heat exchanger inlet pipelines and heat exchanger outlet pipelines. By adopting passive safety technology and passive residual heat removal system, and with the help of top double-layer structure of pressure vessel and break isolation measures, the integrated reactor system according to the present invention can reduce the loss of coolant to the greatest extent, thus meeting the requirements for mitigating design basis accidents, ensuring reactor safety and simplifying the design of the system.
A NUCLEAR REACTOR COMPRISING A REACTOR LID AND AN ADDITIONAL INNER LID
A nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, includes a main vessel with a hot leg and a cold leg, the cold leg encompassing the hot leg; a core submerged in the hot leg; at least one heat exchanger; at least one primary fluid circulation pump pressurizing one of the legs; a reactor lid; a gas plenum; and an inner lid provided beneath the reactor lid to cover the pressurized leg.
A NUCLEAR REACTOR COMPRISING A REACTOR LID AND AN ADDITIONAL INNER LID
A nuclear reactor, in particular a liquid-metal-cooled nuclear reactor, includes a main vessel with a hot leg and a cold leg, the cold leg encompassing the hot leg; a core submerged in the hot leg; at least one heat exchanger; at least one primary fluid circulation pump pressurizing one of the legs; a reactor lid; a gas plenum; and an inner lid provided beneath the reactor lid to cover the pressurized leg.