There is provided a method for measuring a contact force applied to each tube constituting a tube bundle disposed in a fluid from a vibration damping member by using a probe inserted into each tube. Characteristic data defining a relationship between a value measured by the probe and the contact force is previously prepared. Then, the probe is inserted into the tube, and the contact force is calculated using the measurement value of the probe, based on the characteristic data.

An eddy-current flaw detector includes a trace data calculator configured to calculate each coordinate with respect to flaw detection points on which an inspection probe is used upon performing an eddy-current testing based on an inputted condition of eddy-current flaw detection and surface shape data of an inspection-object surface measured by a profilometer, and to calculate a normal vector of each flaw detection point; a gap evaluation calculator configured to acquire an evaluation result on a gap between the inspection-object surface and the inspection probe for each flaw detection point; a flaw detection data collector configured to acquire flaw detection data of an inspection object for each flaw detection point; a flaw detection data analyzer configured to evaluate presence/absence of a flaw in the inspection-object surface based on the flaw detection data of the inspection object and the evaluation result on the gap for each flaw detection point.

An eddy-current flaw detector includes a trace data calculator configured to calculate each coordinate with respect to flaw detection points on which an inspection probe is used upon performing an eddy-current testing based on an inputted condition of eddy-current flaw detection and surface shape data of an inspection-object surface measured by a profilometer, and to calculate a normal vector of each flaw detection point; a gap evaluation calculator configured to acquire an evaluation result on a gap between the inspection-object surface and the inspection probe for each flaw detection point; a flaw detection data collector configured to acquire flaw detection data of an inspection object for each flaw detection point; a flaw detection data analyzer configured to evaluate presence/absence of a flaw in the inspection-object surface based on the flaw detection data of the inspection object and the evaluation result on the gap for each flaw detection point.

A method of creating a computer-generated model of a portion of a nuclear reactor that is positioned between an emitter and a detector of an imaging device. The method includes transmitting energy by the detector emitter toward the containment vessel; receiving at the detector at least a portion of the energy transmitted by the emitter, the at least a portion of the energy being attenuated by a tracing agent in a tube sheet or scattered by the tubesheet of the nuclear reactor within the containment vessel; and creating a computer-generated model of the tubesheet based on the at least a portion of the energy received at the detector, the computer-generated model comprising one or more 3D images of the tubesheet.

A method of creating a computer-generated model of a portion of a nuclear reactor that is positioned between an emitter and a detector of an imaging device. The method includes transmitting energy by the detector emitter toward the containment vessel; receiving at the detector at least a portion of the energy transmitted by the emitter, the at least a portion of the energy being attenuated by a tracing agent in a tube sheet or scattered by the tubesheet of the nuclear reactor within the containment vessel; and creating a computer-generated model of the tubesheet based on the at least a portion of the energy received at the detector, the computer-generated model comprising one or more 3D images of the tubesheet.

An inspection apparatus may include an installation platform and a scan head. The scan head may be configured to engage in an index movement, a theta movement, a wrist fold movement, and a scan movement. During the scan movement, a transducer of the scan head travels a circumferential path so as to allow an inspection of a surface that is opposite of a surface on which the installation platform is mounted. The inspection apparatus may be used to inspect a reactor component in a nuclear reactor.

An inspection apparatus may include an installation platform and a scan head. The scan head may be configured to engage in an index movement, a theta movement, a wrist fold movement, and a scan movement. During the scan movement, a transducer of the scan head travels a circumferential path so as to allow an inspection of a surface that is opposite of a surface on which the installation platform is mounted. The inspection apparatus may be used to inspect a reactor component in a nuclear reactor.

An apparatus for performing an inspection on the beams of the top guide of a BWR includes a housing, an alignment assembly, and an inspection system. The housing is receivable atop the upper edges of a first pair of beams adjacent a receptacle of the top guide. The reception of the housing atop the upper edges of the first pair of beams is facilitated by the alignment assembly which includes a plurality of legs that are simultaneously moved between a retracted position wherein one or more of the legs is disengaged from the beams within the receptacle and an extended position wherein all of the legs are engaged with the beams of the top guide within the receptacle. The inspection system includes a pair of inspection elements that are translated above a second pair of beams that are adjacent the receptacle and that do not have the housing received thereon.

The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

Devices position inspection and operation tools in a nuclear reactor without use of a bridge or other maintenance structure well above the reactor core. Devices can selectively join to in-reactor structures like steam dams through clamping that permits limited movement. Positioning assemblies may be supported by the devices. The positioning assembly includes a mast that moves relative to the positioning assembly. Rollers of the positioning assembly may so move the mast. The positioning assembly may be rotated with a sun gear having an exterior surface about which the mast and rollers can revolve. A local motor or external drive may provide power for this rotation and/or revolving as well as rotation of the rollers to move the mast and assembly. Devices are useable underwater or submerged in fluid and may include instruments with powering lines or mechanical extensions that permit powering or direct interfacing from operators outside the reactor.