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7505545 Method for recognizing step movement sequence of control rod drive mechanism of nuclear reactor  
A method for recognizing the step movement sequence of a control rod drive mechanism of a nuclear reactor, which withdraws and inserts a control rod of a nuclear reactor, includes the steps of:...
7308069 Device and method for controlling the exterior aspect of fuel rods for nuclear reactors  
The invention concerns a device ( 1 ) for controlling the exterior aspect of fuel rods ( 2 ) for nuclear reactors, said device comprising optical means ( 40 ) having at least one camera ( 42, 42′...
7120218 Method for calibrating steam generator water level measurement  
A method is provided for determining and controlling feed water level in a steam generator of a nuclear power plant, whereby the water level sensor is calibrated in terms of the pressure drop...
6895066 Measuring head and measuring assembly for a nuclear fuel rod  
A measuring head is used in measuring an assembly part of a nuclear facility, such as a fuel rod, a fuel assembly box, or a spacer of the fuel assembly. The measuring head is capable of augmenting...
6879653 Method and device for measuring the diameter of a peripheral rod in a fuel assembly of a nuclear reactor  
The diameter of a segment of a peripheral rod in a fuel assembly is measured between two successive spacer grids. A measuring tool is positioned at a level situated between the two successive...
6865244 Device and method for cooling a reactor pressure vessel of a boiling water reactor plant  
In order to allow a reliable and passive external cooling of a reactor pressure vessel of a boiling water reactor, outside the reactor pressure vessel a differential-pressure measurement pipe is...
6782069 In-pile creep test system  
The present invention provides a remote-controlled in-pile creep test system used in in-pile creep tests for measuring and determining mechanical properties of nuclear materials irradiated in...
6707870 Method for determining friction forces occurring on an object moving in a guide on an inaccessible site  
With this method it is possible to evaluate opposing friction forces occurring after a certain operating time on a mobile object in a guide. The method consists of measuring the variations in the...
6668034 Method of inspecting an operation of sealed closure by welding the end of a filling channel traversing the upper plug of a nuclear fuel rod  
A method of inspecting an operation of sealed closure by welding an end opening of a filling channel axially traversing an upper plug for closing the cladding of a fuel rod for a nuclear reactor,...
6639959 Guide tube camera inspection fixture and method of use  
A guide tube inspection camera fixture for inspecting internal surfaces of nuclear reactor control rod guide tubes is provided. In an exemplary embodiment, the guide tube camera fixture includes a...
6606367 Device for measuring the drop time of control rods into the core of a nuclear reactor  
The measurement device comprises a real-time measurement-signal acquisition module ( 25 ) and means ( 23, 24 ) for connecting the cables for picking up the voltage from electrical windings for...
6549600 Method and device for inspecting a fuel element in a nuclear reactor  
A method for inspecting an irradiated fuel element in a nuclear power plant includes the step of measuring, with a measuring device, a spacer of a fuel element for providing measurements of the...
6526114 Remote automated nuclear reactor jet pump diffuser inspection tool  
An inspection apparatus for inspecting welds in a nuclear reactor jet pump includes a probe subassembly rotatably and linearly movably coupled to a frame structure configured to attach to a top...
6449034 Method for controlling perpendicularity of a cylindrical part, such as a nuclear fuel pellet  
In order to control the perpendicularity of a component ( 10 ) such as a nuclear fuel pellet, this component is placed upon a support plane and measurements are taken, by means of two pairs of...
6421405 Monitoring control rod element assembly position  
Compliance with administrative limits on cumulative exposure of control rod groups in the reactor core, is monitored by computing the incremental effective exposure for each group commensurate with...
6404835 Nuclear reactor rod drop time testing method  
A method for measuring the drop time of a rod in nuclear reactor with the rod position indication system coils remaining energized. The signal generated at the coils includes both the rod drop...
6380734 Control element assembly position verification apparatus  
A position verification apparatus comprising a movable member disposed within and movable with respect to a housing containing the movable member, a means for generating a magnetic field within the...
6236699 Method and system for monitoring control rod element assembly position  
Compliance with administrative limits on cumulative exposure of control rod groups in the reactor core, is monitored by computing the incremental effective exposure for each group commensurate with...
6219398 Heated junction thermocouple cable arrangement  
An improved heated junction thermocouple cable arrangement for use with a nuclear reactor heated junction thermocouple having sensors with an unheated thermocouple, a heated thermocouple, and a...
6192096 Magnetostrictive wire control rod position detector assembly  
A magnetostrictive wire control rod position detector assembly which will allow nuclear reactor output to be increased, control performance to be improved, and peripheral equipment to be...
6169776 Methods and apparatus for examining a nuclear reactor shroud  
Methods and apparatus for examining a nuclear reactor shroud are described. In one embodiment the inspection apparatus includes a drive system, a mast subassembly, and a scanner subassembly. The...
6125160 Nuclear fuel bundle spacer envelope dimension measuring system and methods  
The spacer envelope measurement system includes a generally U-shaped fixture having support plates extensible into positions overlying the spacer for supporting the fixture from the spacer....
6118837 Method for detecting the dropping of a control element  
A method for detecting the dropping of at least one control element in a reactor core of a power station by delaying signals output by detectors disposed along a fall path of the control element in...
5978430 Length gauge for in situ measurement of water rod lengths in nuclear fuel bundles and methods of measurement  
The length gauge includes an elongated standards rod, an indicator location block carrying a gauge and an indicator set block. The set block is applied to the location block and the gauge is zeroed...
5963610 CEDM data acquisition system  
A CEDM data acquisition system (40) receives analog coil-current signals from control element drive mechanism coils (18, 20); conditions the analog signals to remove noise induced therein by the...
5956381 Method and apparatus for detecting the dropping of a control element  
A method and an apparatus detect the dropping of at least one control element in a reactor core of a power station by delaying signals output by detectors disposed along a fall path of the control...
5917875 Apparatus for inspecting nuclear fuel assemblies  
Apparatus for rectifying the tendency of a fuel assembly (1) to incline from the perpendicular has a top nozzle support (19) and a base assembly (18) for supporting, respectively, a top nozzle (7)...
5881118 Core protection calculator input filter  
Changes in the value of the control element assembly position signal (26,28) are monitored over a preselected time period, and a determination is made whether these changes conform to a regular,...
5881117 Mid-loop fluid level measuring instrument for a nuclear power plant  
A measurement chamber (18) having an upper and a lower region is at substantially the same elevation as a horizontal pipe (12) having a top region and a bottom region. An equalization line (14)...
5852642 Method and apparatus for inspecting the geometry of a guide tube  
The apparatus is for internal inspection of a guide tube of a nuclear fuel assembly and measurement of deformations of a zone of smaller diameter in a terminal portion of the tube. The apparatus...
5850424 Refueling machine with relative positioning capability  
A refueling machine having relative positioning capability for refueling a nuclear reactor. The refueling machine includes a pair of articulated arms mounted on a refueling bridge. Each arm...
5841824 System and method for testing the free fall time of nuclear reactor control rods  
An improved system and method for testing the free fall time of nuclear reactor control rods. The system employs a plurality of sensor coils which are arranged in tandem along the control rod drive...
5835546 System for seating at least one gasket in a pressure vessel penetration where a column penetrates telescopically  
A system for seating at least one gasket member used to seal a pressure vessel penetration where a column penetrates therethrough includes a tubular member, a column which penetrates through the...
5809100 Apparatus for detecting changes in preload on a tie rod installed as part of a core shroud repair in a boiling water reactor  
In a boiling water reactor having a core shroud disposed within a reactor vessel and a plurality of tie rods installed between vertically spaced sites on the core shroud as part of a core shroud...
5760593 Gap measurement device  
This invention provides a device for capacitively measuring the distance to an object, which comprises an electrode that will couple capacitively with the object, a shield that surrounds the...
5754611 Method and device for measuring at least one characteristic length on a fuel rod arranged at the periphery of a nuclear fuel assembly  
An eddy-current probe (10) is moved in the axial direction of the clad of the rod (1), a first position of the probe (10) is determined in the axial direction, for which a signal from the probe is...
5754609 Condensation vessel for the measurement of steam pressure, filling level and steam flow rate and method for operating a condensation vessel  
A condensation vessel for the measurement of steam pressure includes a steam zone, a steam line which opens in the steam zone at an entrance, a condensate zone which is directly adjacent the steam...
5687204 Method of and apparatus for checking the degradation of a pressure vessel of a nuclear reactor  
In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive...
5661766 Nuclear fuel assembly bow and twist measurement apparatus  
An apparatus for measuring fuel assembly bow and twist comprising a fixturing apparatus, a reference device and an ultrasonic measuring device.
5654639 Induction measuring device in the presence of metal walls  
A device for the measurement by induction of a medium through a metal wall using a transmission portion permitting the induction of a signal in the medium beyond the metal wall and a receiver for...
5644607 Automatic refueling apparatus  
An automatic refueling apparatus has a travel carriage, a traverse carriage and a fuel assembly grappling apparatus composed of a grapple, an extension pipe and a hoist. The automatic refueling...
5610957 Reactor core coolant flow rate control system for a BWR type nuclear power plant  
A reactor core coolant flow rate control system for a BWR type nuclear power plant in which electric power is generated by a turbine-driven generator driven by a steam turbine rotating under the...
5602885 Automated girth weld inspection of nuclear fuel rods  
The girth welds joining the end plugs and the hollow tubes of nuclear fuel rods are inspected automatically using a technique that averages reflectance values, compares the reflectance values to...
5594764 Automated video characterization of nuclear power plant components  
An automated system for determining positions of a plurality of nuclear fuel assemblies organized in an array within a housing of a nuclear power plant includes a radiation hardened, underwater...
5589640 Method for detecting changes in preload on a tie rod installed as part of a core shroud repair in a boiling water reactor  
In a boiling water reactor having a core shroud disposed within a reactor vessel and a plurality of tie rods installed between vertically spaced sites on the core shroud as part of a core shroud...
5586155 Narrow access scanning positioner for inspecting core shroud in boiling water reactor  
A method and an apparatus for inspecting a core shroud by remote operation. The apparatus is a robotic scanning device which can be installed in the narrow space between the core shroud and the jet...
5581586 Drive device for control rod drive mechanisms  
In a drive device of control rod drive mechanisms, a large number of control rod drive mechanisms are divided into a plurality of groups, and there are provided, for each group, a control rod...
5577088 Method and device for ultrasonic examination of faces of the internal surface of the wall of cladding  
The tubular cladding (1) comprises an internal surface of substantially prismatic shape, having successive faces. An ultrasonic examination head (3) makes it possible to emit ultrasound waves in...
5566571 Differential pressure detecting equipment capable of preventing accumulation of non-condensible gases  
A differential pressure detection equipment typically represented by a water level measuring apparatus provided for a nuclear power plant includes a condenser having a steam flow-in port connected...
5568528 Method and system for compensating a rod position indication system for non-linearity  
A method for compensating a rod position indication system for non-linearity comprises the steps of applying an excitation current to a primary of a sensor for inducing a generally linear voltage...
Matches 1 - 50 out of 289 1 2 3 4 5 6 >