摘要:
A nuclear reactor coolant pump (RCP) comprises a stator and a rotating assembly including a rotor, an impeller, and a flywheel configured to rotate about an axis of rotation in response to the stator being electrically energized. The flywheel comprises a first material (such as stainless steel) and has a plurality of mutually parallel tubular openings filled with a second material that is denser than the first material (such as tungsten or tungsten alloy). In some embodiments the mutually parallel tubular openings are cylindrical openings, and are filled with the second material comprising cylindrical rods. In a nuclear reactor including a reactor pressure vessel and a nuclear reactor core comprising fissile 235U disposed in the reactor pressure vessel, the RCP is suitably disposed on or in the reactor pressure vessel with the impeller of the RCP arranged to engage coolant water disposed in the reactor pressure vessel.
摘要:
The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.
摘要:
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.
摘要:
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.
摘要:
A reactor coolant pump (RCP) generates primary coolant flow in a nuclear reactor. The RCP includes a flow amplification device, such as a turbo pump, disposed in the pressure vessel of the nuclear reactor, and an electrically driven pump (e.g. a centrifugal pump). The inlet of the electrically driven pump receives primary coolant water from the pressure vessel and the outlet discharges into the driving inlet of the flow amplification device (e.g. into the turbine of a turbo pump) such that the centrifugal pump drives the flow amplification device to pump primary coolant water. A divider is disposed in the pressure vessel and separates the pumping inlet of the flow amplification device from the pumping outlet of the flow amplification device. The electrically driven pump may include hydraulic drive shaft bearings and starting mechanical drive shaft bearings that disengage at operating speed due to axial shift of the drive shaft.
摘要:
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.
摘要:
A stable startup system 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 stable startup system 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.
摘要:
A nuclear reactor includes a reactor vessel, a containment vessel that surrounds the reactor vessel, and a condenser that receives coolant from within the reactor vessel. The containment vessel and the condenser are at least partially submerged within a common reactor pool of liquid.
摘要:
A reactivity control rod adapted to be used in a reactor core of a fast reactor and disposed at a substantially central portion of the reactor core for controlling a reactivity therein. The reactivity control rod includes a wrapper tube surrounded by a plurality of fuel rods in a reactor core, and a plurality of neutron absorber rods arranged in the wrapper tube. At least one of the plurality of neutron absorber rods includes a cladding tube and a mixture filled in the cladding tube. The mixture is composed of a neutron absorber that absorbs a neutron and a neutron moderator that moderates the neutron.
摘要:
In a nuclear reactor in which a primary coolant is contained, the primary coolant moves upwardly from the core by an operation thereof. An annular steam generator is arranged in an upper side of the core into which the upwardly moving primary coolant flows and transfers heat in the primary coolant into water therein to generate a steam. A passage structure defines a coolant passage for the primary coolant to an outside of the core. The heat-transferred primary coolant in the annular steam generator flows downwardly in the coolant passage so as to flow into the core, thereby moving upwardly. A reactor vessel is arranged to surround the coolant passage so as to contain the core, the annular steam generator and the passage means therein.