Patent classifications
G21C1/32
CHIMNEY STRUCTURE WITH INTERNAL PARTITIONS HAVING A COMMON CENTER, A REACTOR INCLUDING THE CHIMNEY STRUCTURE, AND A METHOD OF MANUFACTURING THE SAME
A chimney structure according to a non-liming example embodiment may include a guide structure defining an opening, and a plurality of chimney partitions including 1 to N chimney partitions concentrically arranged and spaced apart from each other on the guide structure. The 1 to N chimney partitions may each define a curved opening over the opening the guide structure. N may be an integer greater than 1.
Auxiliary condenser system for decay heat removal in a nuclear reactor
A nuclear reactor includes an internal steam generator and a nuclear core disposed in a containment structure. A condenser is disposed outside the containment structure, and includes a condenser inlet line tapping off a steam line connected to the steam generator outside the containment structure, and a condensate injection line conveying condensate from the condenser to the integral steam generator. Isolation valves are located outside the containment structure on a feedwater line, the steam line, and the condensate injection line. The valves have an operating configuration in which the isolation valves on the feedwater and steam lines are open and the isolation valve on the condensate injection line is closed, and a heat removal configuration in which the isolation valves on the feedwater and steam lines are closed and the isolation valve on the condensate injection line is open.
Cooling facility in a reactor vessel and electric power generation system
An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.
Integral pressurized water reactor with compact upper internals assembly
An integral pressurized water reactor (PWR) comprises: a cylindrical pressure vessel including an upper vessel section and a lower vessel section joined by a mid-flange; a cylindrical central riser disposed concentrically inside the cylindrical pressure vessel and including an upper riser section disposed in the upper vessel section and a lower riser section disposed in the lower vessel section; steam generators disposed inside the cylindrical pressure vessel in the upper vessel section; a reactor core comprising fissile material disposed inside the cylindrical pressure vessel in the lower vessel section; and control rod drive mechanism (CRDM) units disposed inside the cylindrical pressure vessel above the reactor core and in the lower vessel section. There is no vertical overlap between the steam generators and the CRDM units.
Managing nuclear reactor control rods
A nuclear reactor control rod drive assembly includes a control rod drive mechanism coupled to a drive shaft and operable to bi-directionally urge the drive shaft through a portion of an inner volume of a reactor vessel at a first force; a control rod manifold coupled to the drive shaft; a plurality of control rods coupled to the control rod manifold, the plurality of control rods adjustable among a plurality of positions within the inner volume of the reactor vessel based on operation of the control rod drive mechanism; and at least one variable strength joint positioned between the control rod drive mechanism and the plurality of control rods.
Compact integral pressurized water nuclear reactor
A pressurized water reactor (PWR) includes a cylindrical pressure vessel defining a sealed volume, a nuclear reactor core disposed in a lower portion of the cylindrical pressure vessel, one or more control rod drive mechanisms (CRDMs) disposed in the cylindrical pressure vessel above the nuclear reactor core, and an annular steam generator surrounding the nuclear reactor core and the CRDM. In some such PWR, a cylindrical riser is disposed coaxially inside the pressure vessel and inside the annular steam generator and surrounds the nuclear reactor core and the CRDM, and the steam generator is disposed coaxially inside the cylindrical pressure vessel in an annular volume defined by the cylindrical pressure vessel and the cylindrical riser. In other such PWR, the steam generator is disposed coaxially outside of and secured with the cylindrical pressure vessel.
Liquid fuel nuclear fission reactor
Disclosed embodiments include nuclear fission reactors, nuclear fission fuel pins, methods of operating a nuclear fission reactor, methods of fueling a nuclear fission reactor, and methods of fabricating a nuclear fission fuel pin.
Liquid fuel nuclear fission reactor
Disclosed embodiments include nuclear fission reactors, nuclear fission fuel pins, methods of operating a nuclear fission reactor, methods of fueling a nuclear fission reactor, and methods of fabricating a nuclear fission fuel pin.
Nuclear reactor integrating a safety primary heat exchanger
A nuclear reactor includes a vessel incorporating at least one primary power heat exchanger for cooling the primary liquid of the nuclear reactor during the normal operation of the reactor and at least one primary passive safety heat exchanger for cooling the primary liquid of the nuclear reactor in the event of a malfunction in the normal cooling of the primary liquid of the reactor. The vessel includes a compartment arranged in the thickness thereof, wherein the primary passive safety heat exchanger is at least partially contained inside the compartment.
Nuclear reactor integrating a safety primary heat exchanger
A nuclear reactor includes a vessel incorporating at least one primary power heat exchanger for cooling the primary liquid of the nuclear reactor during the normal operation of the reactor and at least one primary passive safety heat exchanger for cooling the primary liquid of the nuclear reactor in the event of a malfunction in the normal cooling of the primary liquid of the reactor. The vessel includes a compartment arranged in the thickness thereof, wherein the primary passive safety heat exchanger is at least partially contained inside the compartment.