F22B37/002

Anti-vibration tube support plate arrangement for steam generators

A means of offsetting semi-circular tube support plates typically present in heat exchangers with cross flow baffles, such as axial flow economizers, utilizing the motive force of steam generator pressurization. The offset slightly flexes the tubes, thereby providing a preload which minimizes the potential for tube vibration and wear.

PRESSURE VESSEL

A pressure vessel having a diameter greater than or equal to 1 m and made by laser cladding an inner surface of the vessel, the laser cladding following a helical path.

TUBE SUPPORT SYSTEM FOR NUCLEAR STEAM GENERATORS

Apparatus for a steam generator that employs tube support plates within a shroud that is in turn disposed within a shell. The tube support plates are made of a material having a coefficient of thermal expansion lower than that of the shroud. The tube support plates are aligned during fabrication, with minimal clearances between components. Using a tube support displacement system, a controlled misalignment is then imposed on one or more tube support plates, as the steam generator heats up. The tube support plate displacement system has only one part, a push rod, which is internal to the steam generator shroud, thereby minimizing the potential of loose parts. The tube support plate displacement system can be used to provide controlled misalignments on one or more tube support plates, in the same or varying amounts and directions, and with one or more apparatus for each individual tube support plate.

Neutron absorbing apparatus

A neutron absorbing insert for use in a fuel rack. In one aspect, the insert includes: a plate structure having a first wall and a second wall that is non-coplanar to the first wall; the first and second walls being formed by a single panel of a metal matrix composite having neutron absorbing particulate reinforcement that is bent into the non-coplanar arrangement along a crease; and a plurality of spaced-apart holes formed into the single panel along the crease prior to bending.

FLOW CONDITIONING DEVICE FOR STEAM GENERATOR

Disclosed is an apparatus and method for conditioning fluid flow in a nuclear power plant steam generator. A flow conditioning device includes an outer enclosure defining a plurality of entrance apertures arranged in an array and a plurality of exit apertures arranged in an array. A plurality of baffle plates are defined within the outer housing. The baffle plates define flow channels in fluid communication with the entrance and exit apertures to create a flow path of alternating directions. The flow channels receive fluid flow from the plurality of entrance apertures, direct the fluid flow from the entrance apertures in alternating directions through the flow channels to impart turning and frictional pressure loss to the fluid flow, and direct exiting fluid flow through the exit apertures into the tubelane region of the steam generator.

Device and method for removing foreign object from heat transfer tube

Proposed are device and method for removing a foreign object from a heat transfer tube, and the device includes a reel part configured to wind or unwind a connecting tube, a drive part, disposed adjacent to the reel part, configured to move the connecting tube in and out of a heat transfer tube, and to operate so that the connecting tube is rotatable inside the heat transfer tube, and a manipulator, disposed on an end part of the connecting tube, configured to be inserted into the heat transfer tube and to remove a foreign object placed between the heat transfer tube and an adjacent heat transfer tube, wherein the manipulator is configured to hold and transport at least a portion of the foreign object.

Method of detecting an existence of a loose part in a steam generator of a nuclear power plant
12537112 · 2026-01-27 · ·

A plurality of signal anomalies are identified in a number of tubes in a steam generator. Since the geometry of the steam generator is known, the location of each signal anomaly along each tube is converted into a location within the interior of the steam generator. If a plurality of signal anomalies are at locations within the steam generator that are within a predetermined proximity of one another, such a spatial confluence of signal anomalies is determined to correspond with a loose part situated within the steam generator. Additional methodologies can be employed to confirm the existence of the loose part. Historic tube sheet transition signal data can be retrieved and subtracted from present signals in order to enable the system to ignore the relatively strong eddy current sensor signal of a tube sheet which would mask the relatively weak signal from a loose part at the tube sheet transition.

COMBINED CYCLE NUCLEAR POWER PLANT
20260132921 · 2026-05-14 ·

A nuclear power plant comprising at least one nuclear reactor having a steam generator, a steam cycle including the steam generator, a first turbine fluidly coupled to the steam generator, a first condenser fluidly coupled to the first turbine, and a feedwater heater fluidly coupled to the first condenser and the steam generator, an intermediate thermal loop including the first condenser, and an evaporator, and an organic cycle including the evaporator, a second turbine fluidly coupled to the evaporator, a second condenser fluidly coupled to the second turbine, and a heat exchanger fluidly coupled to the second condenser and the evaporator.