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| Number | Title | Issue Date |
| 7291549 | Method and structure to reduce risk of gold embrittlement in solder joints A method for reducing gold embrittlement in solder joints, and a copper-bearing solder according to the method, are disclosed. Embodiments of the invention comprise adding copper to non-copper based solder, such as tin-lead solder. The embodiments may further compri... | 11/06/2007 |
| 7249885 | Heat flux measuring device for pressure pipes, method for producing a measuring device, method for monitoring an operating state of a heat exchanger, heat exchanger and method for measuring a heat flux A measuring device for a heat exchanger includes a heat exchanger pressure pipe having a pipe wall with a circumference, and an indentation extending over and deforming a portion of the circumference. At least one thermocouple is disposed eccentrically in the portio... | 07/31/2007 |
| 7124645 | Magnetic-inductive measuring device for flowing substances and method for its production The invention relates to a magnetic-inductive measuring device (1) for flowing substances (substance being measured), with a measuring tube (2) and a further subsystem respectively for recording measuring signals, com... | 10/24/2006 |
| 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 across structural components in the feed water path. The water level diffe... | 10/10/2006 |
| 7056013 | Sensor arrangement having an air inflow pattern for preventing direct debris impact A temperature sensor arrangement (100, 300) includes a sensor cavity (150), a temperature sensing element (330) being positioned along a center line (140, 340) of the sensor cavity (150) and generating a signal indicating temperatu... | 06/06/2006 |
| 7005745 | Method and structure to reduce risk of gold embrittlement in solder joints A method for reducing gold embrittlement in solder joints, and a copper-bearing solder according to the method, are disclosed. Embodiments of the invention comprise adding copper to non-copper based solder, such as tin-lead solder. The embodiments may further compri... | 02/28/2006 |
| 6931952 | Device for in-line measurement of properties of fluid flows in pipeline systems A device called “pill” is provided for in-line measurement of properties, such as pressure and temperature, in a fluid flow within a pipeline system. The device is small enough to travel in the medium of the pipeline system in an unrestricted manner. It has at l... | 08/23/2005 |
| 6876715 | Measurement system of torsion vibration for reactor internal pump Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector 2 that detects vibration in the radial direction, and the sou... | 04/05/2005 |
| 6751281 | Measurement system of torsion vibration for reactor internal pump Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector 2 that detects vibration in the radial direction, and the sou... | 06/15/2004 |
| 6721383 | Maximum extended load line limit analysis for a boiling water nuclear reactor A computerized method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at core flows lower than normal operating parameters is provided. The operating domain is characterized by a map of the reactor the... | 04/13/2004 |
| 6504888 | Apparatus and methods of flow measurement for a boiling water reactor internal pump A reactor pressure vessel (RPV) for a nuclear reactor that permits measurement of the flow through each reactor internal pump (RIP) is described. The reactor pressure vessel also includes at least one reactor internal pump that includes an impeller and a ... | 01/07/2003 |
| 6216728 | Tunable anticipatory output response valve control A valve control apparatus for generating an anticipatory output response for controlling a fluid flow in a fluid flow line includes a valve provided inside the fluid flow line, at least one sensor for providing at least one input signal, said at least one... | 04/17/2001 |
| 6163588 | Core plate and reactor internal pump differential pressure lines for a boiling water reactor A modular differential pressure measuring system for a boiling water nuclear reactor pressure vessel is described. The modular pressure differential system includes a plurality of pressure lines having a plurality of pressure line sections. The system als... | 12/19/2000 |
| 6061412 | Nuclear reaction protection system A safety grade protection system for monitoring parameters indicative of the status of a core of a nuclear reactor, and reducing the criticality of the nuclear reaction when the onset of unsafe conditions are detected. The invention directly detects, in r... | 05/09/2000 |
| 5930317 | Power range monitor system for nuclear reactor A power range monitor apparatus includes a plurality of average power range monitors for calculating/monitoring local power values, average reactor power values, and core flow rate values, a plurality of rod block monitors for monitoring the average value... | 07/27/1999 |
| 5828712 | Coolant water flow rate test with rubidium nuclear tracer for reactors Fluid flow rates are determined with a nonradioactive tracer agent in the operation of a water cooled nuclear fission reactor employed for driving electrical power generators. The technique is proposed for use to routinely calibrate other flow measuring m... | 10/27/1998 |
| 5682410 | Method for determining core flow rate and water temperature/density in boiling water reactor A method for determining the core flow rate from pump differential pressure method equations and a heat balance equation for determining the temperature and density of the reactor water in the downcomer and lower plenum region. The measured reactor water ... | 10/28/1997 |
| 5559293 | Steam generation system mass and feedwater control system In a steam generator or boiler of the type having a pressure vessel having a zone in which heated water and steam can be separated, an outlet for the flow of pressurized steam and an outlet for the flow of liquid, a riser section in which fluid passes for... | 09/24/1996 |
| 5537450 | On-line analysis of fuel integrity Failed fuel cladding in light water reactors can lead to premature reactor shutdown for removal of the failed fuel bundles from the core. The lost power and associated fuel replacement costs are astronomically high, approaching a million dollars per day i... | 07/16/1996 |
| 5535253 | Method and device for detecting leaks in penetrations of a nuclear reactor vessel head during operation The method and the device are applicable to the penetrations (2) of a pressurised water nuclear reactor vessel head (1) during operation. The device includes a double circuit for picking off two gas samples (100, 16, 17; 12, 13, 14, 15) and a measurement assem... | 07/09/1996 |
| 5502753 | Instrumentation probe An instrumentation probe for measuring and recording one or more physical parameters within a fluid duct, such as a nuclear reactor fuel channel, comprises one or more sensors responsive to the parameters to be measured and recorded, each sensor actuating... | 03/26/1996 |
| 5490184 | Method and a system for accurately calculating PWR power from excore detector currents corrected for changes in 3-D power distribution and coolant density Excore detector measurements are used to generate on-line absolute reactor power in a pressurized water reactor (PWR) by calibrating detector current measurements to the reactor thermal power calculation made at a base time early in reactor cycle while th... | 02/06/1996 |
| 5467375 | Gas injection system of nuclear power plant and gas injection method therefor A gas injection system of a nuclear power plant including a reactor and a gaseous waste disposal system, comprises a hydrogen injection unit for injecting hydrogen into a reactor of a nuclear power plant, an oxygen injection unit for injecting oxygen into... | 11/14/1995 |
| 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 hygroscopic portion (48), the electrical resistance of which cha... | 09/05/1995 |
| 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 cylindrical housing. A signal cable is coupled to the vibra... | 08/15/1995 |
| 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 comprises a rotor (304) which can modulate the flux (206) of th... | 06/13/1995 |
| 5396524 | Flow measurement probe A flow measurement probe measures reactor coolant water flow in a cold leg pipe of a nuclear reactor system wherein a lack of elbows precludes the use of elbow tap flow measurements. An elongated probe body disposed in the pipe includes a common dynamic p... | 03/07/1995 |
| 5333158 | Device and method for the measurement of the neutron flux in the core of a nuclear reactor The device comprises a mobile probe which can be displaced inside thimbles. A plurality of ducts (20) for the passage and support of a thimble are disposed in the partitioning (6) of the reactor, around the core (4) along an axial direction and substantia... | 07/26/1994 |
| 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. A first gas flows through the nozzle and then into and thr... | 01/18/1994 |
| 5265478 | Fluid flow monitoring device A flow meter and temperature measuring device comprising a tube with a body centered therein for restricting flow and a sleeve at the upper end of the tube to carry several channels formed longitudinally in the sleeve to the appropriate axial location whe... | 11/30/1993 |
| 5245640 | Nuclear fuel rod end plug pressurization hole inspection apparatus To inspect the integrity of pressurization holes in nuclear fuel rod final end plugs, quality assurance apparatus includes an adapter providing a test chamber into which an end plug is inserted. Instrument gas is introduced into the test chamber through a... | 09/14/1993 |
| 5215704 | Method and apparatus for in situ testing of heat exchangers Using the method of this invention, the performance of a heat exchanger is determined by measuring the heat transfer capabilities of an individual tube. A relatively small reservoir of service fluid is connected to the inlet and outlet ports of a tube. Th... | 06/01/1993 |
| 5118461 | Flow rate measuring apparatus In an apparatus including a fluid circulation unit for allowing a fluid in a container to be circulated along a passage in the container, a flow rate measuring apparatus includes a rotational speed transducer for detecting the rotational speed of a motor ... | 06/02/1992 |
| 5108694 | Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel A system for measuring the power distribution in a reactor core includes a plurality of gamma detectors disposed outside of the reactor vessel which houses the reactor core. The gamma detectors correspond in number to the number of instrumentation tubes i... | 04/28/1992 |
| 5064603 | Hydroball string sensing system A hydroball string sensing system for a nuclear reactor that includes stainless tubes positioned to guide hydroball strings into and out of the nuclear reactor core. A sensor such as an ultrasonic transducer transmitter and receiver is positioned outside ... | 11/12/1991 |
| 5064604 | Cost effective fluid line status sensor system A sensor assembly comprising a rod-shaped thermally conductive element oriented radially with respect to a flow pipe and two or more thermocouples installed on the thermally conductive element. A first end of the thermally conductive element is arranged i... | 11/12/1991 |
| 5024802 | Method for steam generator water level measurement A method is provided for determining and controlling steam water level in a steam generator of a nuclear plant, comprising calibrating the water level sensor in terms of velocity head and also adjusting the high level setpoint in terms of a velocity head ... | 06/18/1991 |
| 4975239 | BWR core flow measurement enhancements An apparatus and process for the accurate measurement and calibration of core flow in a boiling water reactor is disclosed. The reactor includes a pressure vessel having internal forced circulation through the core. An annular downcomer region establishes... | 12/04/1990 |
| 4967603 | Inductive flow probe for measuring the flow velocity of a stream of liquid metal An inductive flow probe for measuring the flow velocity of a stream of liquid metal by insertion of the probe into the stream. The probe includes a probe tube having first and second regions therein, at least one permanent magnet disposed in the first reg... | 11/06/1990 |
| 4958523 | Apparatus for measuring the flow rate of electrically conductive liquids An apparatus for measuring the flow rate of electrically conductive liquids includes two coils disposed in succession as seen in the flow direction of a liquid. The coils are switched in alternation as a primary and a secondary coil. One of the coils is e... | 09/25/1990 |
