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5490418 |
Device for measuring the force exerted by a grid spring
A device for measuring the force exerted by a spring of a supporting grid on a fuel rod passing through the grid has an elongate body connected by two flexible blades that are parallel to the long...
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5485491 |
Online diagnostic system for rotating electrical apparatus
An online system for diagnosing operability of a rotating electrical apparatus includes sensors producing electrical variables corresponding to operating conditions of the apparatus, data...
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5483560 |
Method and apparatus for testing, repairing or exchanging the nozzles passing through the bottom of a reactor pressure vessel
A method and an apparatus for testing, repairing or exchanging nozzles of the bottom of a reactor pressure vessel include inserting individual shielding containers into the reactor pressure vessel....
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5473647 |
Process and device for obtaining samples from the atmosphere in a closed gastight vessel, preferably from the reactor safety vessel of a nuclear power station
A process for obtaining a sample from an atmosphere in a closed gastight vessel, preferably from a reactor safety vessel of a nuclear power station, includes passing a sample through a venturi...
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5473644 |
Apparatus for measuring power of nuclear reactor and method for manufacturing the same
An apparatus for measuring the power of a nuclear reactor having a sensor assembly disposed in a core section inside the nuclear reactor. The sensor assembly includes a cover tube made of metal and...
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5465278 |
Shroud electrochemical potential monitor
A method and an apparatus for measuring the degree of intergranular stress corrosion cracking protection in the area of the core shroud weldments. Electrochemical potential sensors are attached to...
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5465279 |
Reactor coolant pump seal test decontamination housing
An arrangement of reactor coolant pump seals arranged in a generally annular stack with a plurality of stacking spacers in a test housing for emplacement in a chemical decontamination test loop...
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5459767 |
Method for testing the strength and structural integrity of nuclear fuel particles
An accurate method for testing the strength of nuclear fuel particles. Each particle includes an upper and lower portion, and is placed within a testing apparatus having upper and lower compression...
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5448603 |
Pressure-sensitive variable-resistance hygroscopic fluid detector, and method
A fluid detector (20) has an enclosure (32) defining an internal chamber (33). The enclosure has a frangible wall portion (34). A sensor (46) is arranged within the chamber. The sensor has a...
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5446774 |
Spud finger gauge
A tool for checking the required spacing between adjacent fingers of the spud in a control rod drive. The tool is a GO-NO-GO gauge with tight tolerance. The spud finger gauge has two circular...
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5444746 |
Contamination inspecting device for portable articles
The invention provides an improved contamination inspecting device which can carry out continuous, automatic inspection of portable articles both large and small regardless of their shape. The...
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5442665 |
Strain gauge instrumentation device for in-core monitor housings
A device for easily installing and removing strain gauge instrumentation and associated wiring on the inside of in-core monitor housings. A vibration sensor is attached to an inside diameter of a...
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5425064 |
Nuclear turbine coolant flow meter
Coolant flow (900) in the core (103) of a natural circulation boiling water reactor (100) is monitored by making use of a detector (208) for nuclear radiation and a turbine device (204) which...
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5422920 |
Crystal grain size estimating method for nuclear fuel pellets
A method of estimating the crystal grain size of a nuclear fuel pellet. A plurality types of UO 2 powders are heated at a predetermined temperature raising speed in dry air so as to measure weight...
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5418823 |
Combined ultrasonic and eddy-current method and apparatus for non-destructive testing of tubular objects to determine thickness of metallic linings or coatings
A combined ultrasonic and eddy-current method and apparatus for non-destructively determining the liner thickness of a zirconium liner provided at the inner surface of a zirconium alloy nuclear...
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5408509 |
Automatic pressure vessel servicing apparatus
A method and apparatus for positioning stud affecting apparatus comprising: sequentially positioning a plurality of flange cover sectors about the flange of a nuclear pressure vessel; rotating each...
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5398268 |
Nuclear power plant having a water chemistry control system for a primary cooling system thereof and an operation method thereof
A water chemistry factor which is specific to a specific portion of a primary cooling system and universal is decided to be a standard target. The concentration of an agent for mitigating corrosion...
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5394446 |
Uncoupling rod centering gauge
A gauge for ensuring that the uncoupling rod of a control rod drive is properly inserted in the center hole of the spud and not in one of the outer lobes, i.e., spud flow holes, which communicate...
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5386442 |
Method and apparatus for controlling the load on double cantilever beam sensors
An apparatus and a method for measuring and controlling the crack growth rate within a double cantilever beam type test specimen. The arms of the test specimen are fitted with a pressure-actuated...
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5377236 |
Method and apparatus for measuring rod end squareness
A method and apparatus measure squareness of an end of a rod relative to a longitudinal centerline axis thereof without requiring rotation of the rod. The apparatus includes a flat plate mounted...
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5377237 |
Method of inspecting repaired stub tubes in boiling water nuclear reactors
An ultrasonic method of inspecting repaired stub tubes in a boiling water reactor. The top and bottom ends of each stub tube are respectively welded to the corresponding control rod drive housing...
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5377235 |
Control rod canopy seal positioning and welding system
A system is directed for remotely securing a canopy seal about a broken omega seal site between the control drive mechanism and the adapter tube of a nuclear reactor vessel so as to contain any...
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5375756 |
Apparatus for assembling and welding final end plugs to nuclear fuel-containing cladding tubes and inspecting the welds, all on an automated basis
In an automated final weld apparatus, a transporter conveys nuclear fuel-loaded cladding tubes successively to a check station to verify the presence of a plenum spring in the open end of each...
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5377234 |
Colloidal resin slurry recycle concentrating system of nuclear reactor coolant water
An analytical testing means for determining the ion contents of nuclear reactor coolant water comprising ion chromatograph means and a conductivity detector. Reagent containing ion exchange resin...
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5369677 |
Device for materials testing in nuclear reactors
A testing device for load-testing of specimens (3) in a nuclear reactor environment is attached to one of the pipes (1) of the reactor for conveying a first medium under pressure and provides a...
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5369674 |
Plant diagnosis apparatus and method
This invention concerns a plant diagnosis apparatus which comprises a first detecting unit for detecting a state of devices constituting a circulating system in which a fluid circulates and a...
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5369675 |
Remote load activating mechanisms
Electrically controlled load activating mechanisms that can be used inside the containment vessel of a nuclear reactor in conjunction with bellows-loaded DCB crack growth sensors installed inside...
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5367546 |
Fluid sampling system for a nuclear reactor
A system of extracting fluid samples, either liquid or gas, from the interior of a nuclear reactor containment utilizes a jet pump. To extract the sample fluid, a nonradioactive motive fluid is...
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5361284 |
Tube corrosion accelerator
A device for creating a corrosive condition and monitoring that condition, adapted for use in active fluid heat exchangers, has a sealed tube having corrosion sites spaced apart on its exterior....
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5344302 |
Remote impression tool
A tool for remotely obtaining an impression of a component surface. A support pole is used to position a mold plate having side walls against a component surface. One or more locating guides are...
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5345478 |
Method and device for non-destructive examination of a wall of a tank containing a radioactive liquid
The tank contains a liquid in which a radioactive element emitting gamma radiation is distributed substantially uniformly. A photon detector (15) is disposed in the vicinity of the external surface...
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5341678 |
Method for determining thickness of ferromagnetic material deposition on nuclear fuel rods
A method for determining the thickness of ferromagnetic material deposited on a nuclear fuel rod. Calibration samples of known thickness and known permeability are placed between the probe of an...
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5343504 |
Nuclear fuel bundle spacer spring constant gauge
To measure the spring constants of double-acting, fuel rod-centering springs assembled with different pairs of ferrules in a nuclear fuel bundle spacer, a gauge is provided to include an alignment...
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5339339 |
Process for carrying out an inspection round of nuclear installations
Process for carrying out an inspection or monitoring round of a nuclear site (5) consisting of recording in a central computer (22) connected to a radiofrequency transmitter/receiver or transceiver...
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5329465 |
Online valve diagnostic monitoring system
An online valve monitoring system senses operational characteristics of a valve and provides a diagnosis of aberrations in the characteristics. Sensors, coupled to a valve, supply sensor signals as...
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5329561 |
Device for checking the thickness and the cohesion of the interface of a duplex tube
The duplex tube (1) comprises a tubular core (2) and a cladding or covering layer (3) made from an alloy, the base metal of which is identical to the base metal of the alloy constituting the...
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5319683 |
Calibration arangement and method of calibrating an inspection instrument
Calibration arrangement and method for calibrating an inspection instrument, such as an ultrasonic inspection instrument of the kind typically used to inspect nuclear reactor pressure vessels. The...
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5316633 |
Method and apparatus for measuring sensitization of structural members
A method and system for electrochemically measuring the sensitization to stress corrosion cracking of small pipes of plant structural members in a very short period of time. A micro electrochemical...
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5307385 |
Method of and apparatus for estimating remaining service life of material being exposed to radiant ray irradiation
A method and an apparatus for estimating the remaining service life of an object by measuring the physical quantity of a sample and which are applicable to a nuclear reactor. A plurality of model...
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5282229 |
Method and apparatus for measuring gap between adjoining fuel rods of fuel assembly
A gap between adjoining fuel rods arranged in a fuel assembly is measured by setting a measuring device into a fluid such as cooling water or a specific gas such as CF filling a container, placing...
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5280507 |
Method and apparatus for sensing obstructions in a nuclear fuel rod
A method and apparatus of sensing obstructions in a tubular nuclear fuel rod or the like is disclosed. A nozzle is positioned to engage one end of the fuel rod in an air tight sealed relationship....
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5272738 |
Device for monitoring the atmosphere withing a nuclear reactor containment
In a device for monitoring the atmosphere within the containment shell (1) of a reactor plant, a sample removal means (41) is provided in the containment shell, from which a gas mixture is led via...
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5267282 |
Device for monitoring the stack exit air in a reactor installation
A device for monitoring the stack exit air in a reactor installation consists essentially of a pressure relief line (2) which connects the containment vessel (1) to the stack (5) and in which a...
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5265035 |
System diagnostics using qualitative analysis and component functional classification
A method for detecting and identifying faulty component candidates during off-normal operations of nuclear power plants involves the qualitative analysis of macroscopic imbalances in the...
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5265130 |
Cell-size inspection device for nuclear fuel assembly
In the nuclear fuel assembly, a plurality of plate-shaped straps are assembled perpendicularly to each other into a grid shape so as to construct a supporting grid providing with a plurality of...
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5263060 |
Segmented instrumentation tube including a locking sleeve for interlocking the segments of the instrumentation tube
Segmented instrumentation tube including a locking sleeve for interlocking the segments of the instrumentation tube, so that the threaded ends of the instrumentation tube do not unthread when...
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5257545 |
Method and apparatus to monitor check valves
A non-intrusive vibration measurement system and method using commercial ultrasonic instruments together with digital signal filtering and analysis techniques is adapted to quantitatively detect...
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5255295 |
Device for measuring the temperature of the primary coolant of a nuclear reactor, with accelerated internal flow
The measurement device (3) comprises a metallic body (5) fixed in the wall of a reactor coolant pipe (1). The metallic body (5) is pierced in order to constitute a first channel (8) communicating...
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5253276 |
Dual-longitudinal-mode ultrasonic testing
A method of ultrasonic inspection of a reactor nozzle involves positioning emitter and receiver transducers on the exterior vessel wall near the nozzle. The emitter transducer is positioned and...
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5251242 |
Bi-metallic, self powered, fixed incore detector, and method of calibrating same
The present invention is a detector assembly for a nuclear reactor which includes platinum detector segments (30-40) axially distributed end to end within a reactor assembly and vanadium detector...
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