G21C17/017

Water jet peening apparatus and water jet peening method

Provided is a water jet peening apparatus and a water jet peening method including: a clamping cylinder (201) which is able to be disposed at the outer peripheral side of an instrumentation nozzle (83) with a predetermined gap therebetween; a clamping piece (210) which is able to fix the clamping cylinder (201) to the instrumentation nozzle (83); a nozzle guide (221) which has a cylindrical shape, is provided inside the clamping cylinder (201), and is positioned to a position adjacent to the upper end of the instrumentation nozzle (83); an inner surface WJP nozzle (105) which is movable upward and downward inside the nozzle guide (221); and a drainage hole (224) which radially penetrates the nozzle guide (221). Accordingly, it is possible to improve the safety of the operation by preventing a thimble tube from being popped out due to a water jet peening operation.

Water jet peening apparatus and water jet peening method

Provided is a water jet peening apparatus and a water jet peening method including: a clamping cylinder (201) which is able to be disposed at the outer peripheral side of an instrumentation nozzle (83) with a predetermined gap therebetween; a clamping piece (210) which is able to fix the clamping cylinder (201) to the instrumentation nozzle (83); a nozzle guide (221) which has a cylindrical shape, is provided inside the clamping cylinder (201), and is positioned to a position adjacent to the upper end of the instrumentation nozzle (83); an inner surface WJP nozzle (105) which is movable upward and downward inside the nozzle guide (221); and a drainage hole (224) which radially penetrates the nozzle guide (221). Accordingly, it is possible to improve the safety of the operation by preventing a thimble tube from being popped out due to a water jet peening operation.

SYSTEMS AND METHODS FOR CONTINUALLY MONITORING THE CONDITION OF NUCLEAR REACTOR INTERNALS

A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.

Water jet peening apparatus and method, and method of evaluating nozzle

A water jet peening apparatus includes: a nozzle, which is arranged in water and has a mouth from which water is jetted out; a detecting device, which is arranged in the water and detects sound in at least a part of a period during which the water is being jetted out from the mouth; and a processing device, which determines, based on a result of the detection by the detecting device, presence or absence of abnormality in the nozzle.

Apparatus and method to remotely inspect piping and piping attachment welds

An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned.

Apparatus and method to remotely inspect piping and piping attachment welds

An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned.

ARTICULATED MANIPULATOR FOR NAVIGATING AND SERVICING A HEAT EXCHANGER
20210383937 · 2021-12-09 · ·

A manipulator configured to navigate a heat exchanger including a plurality of tubes extending through a tubesheet is disclosed herein, the manipulator including a first end effector, a second end effector, and an articulation assembly. The first end effector is configured to accommodate an instrument configured to service the heat exchanger and includes a first actuator configured to extend a first gripper into a tube of the plurality of tubes. The second end effector includes a second actuator configured to extend a second gripper into a tube of the plurality of tubes. The first and second gripper are configured to secure the manipulator to the tubesheet, and, when the second gripper is securing the manipulator to the tubesheet, the articulation assembly is configured to enable the first end effector to move relative to the second end effector in a plane that is parallel to the tubesheet.

METHOD FOR THERMAL SLEEVE ELIMINATION

Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve.

MODULAR KINEMATIC AND TELEMETRY SYSTEM FOR AN IRRIGATION SYSTEM
20220192111 · 2022-06-23 ·

A modular kinematic and telemetry system for an irrigation system includes a condition-based monitoring (CBM) system and a plurality of sets of modular foot assemblies. The CBM system has a housing and supports a plurality of kinematic and telemetry components. The plurality of sets of modular foot assemblies includes a first set and a second set that secure to the housing of the CBM system. The first set is configured to secure the CBM system to a first end gun configuration and the second set is configured to secure the CBM system to a second end gun configuration that is different from the first end gun configuration.

Optical fiber laser induced breakdown spectroscopy detection device and method

An optical fiber laser induced breakdown spectroscopy detection device and a detection method are provided. The device comprises an optical fiber LIBS detector and a master control detection system. The master control detection system is installed in the master control room of a nuclear power plant, and the optical fiber LIBS detector is configured to perform detection in a pipeline. The master control detection system and the optical fiber LIBS detector are connected to each other via the transmission optical fiber and the control signal line. The remote on-line detection of the positioning and fixed point of the designated area of the inner wall of the main pipeline of the nuclear power plant can be detected on line in the master control room of the nuclear power plant.