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Match Document Document Title
8957781 Real time monitoring system of spent fuel pool and method thereof  
A real time monitoring system of a spent fuel pool includes a detection unit configured to detect condition information using a sensor installed in the spent fuel pool; an input storage unit...
8903034 Fuel rod internal pressure measurement  
A method for determining a leaking nuclear fuel rod that remotely measures the internal pressure in the plenum region of the fuel rod by remotely measuring the thermal response of the rod when a...
8891723 Stable startup system for a nuclear reactor  
A nuclear reactor module includes a reactor vessel containing coolant, a reactor core submerged in the coolant, and a heat exchanger configured to remove heat from the coolant. The nuclear reactor...
8868739 Filtering recorded interactions by age  
Systems and methods for the forming of user device groups are presented. First, logical relationship information can be recorded, the logical relationship information describing logical...
8842796 Nuclear fuel rod pellet stack inspection  
A method of detecting defects in nuclear fuel within a fuel rod that first heats the fuel rod to a temperature substantially above the ambient temperature. The surface temperature of the fuel rod...
8831162 Apparatus and method for measuring a temperature of coolant in a reactor core, and apparatus for monitoring a reactor core  
A reactor core coolant temperature measuring apparatus for measuring the temperature of the coolant flowing in the reactor core of a nuclear reactor comprises a γ-ray thermometer having a...
8761329 Rod position detection apparatus and method  
An improved apparatus for determining the position of a drive rod within the interior of a drive rod housing includes a transmission antenna at one location on the housing and a receiving antenna...
8644443 Gamma thermometer axial apparatus and method for monitoring reactor core in nuclear power plant  
A pair of linear arrays of gamma thermometer (GT) sensors arranged in a nuclear reactor core including: a first linear array of GT sensors, wherein the GT sensors are arranged asymmetrically along...
8599987 Wireless transmission of nuclear instrumentation signals  
A method of monitoring a condition of a nuclear reactor pressure vessel disposed in a radioactive environment is provided. The method includes the steps of sensing a condition of the reactor...
8571163 Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor  
A method for monitoring and acoustic damping a boiling water reactor which includes: a reactor pressure vessel; a steam pipe for transporting steam out from a steam dome of the reactor pressure...
8514998 Induction heating stress improvement  
In implementing an induction heating stress improvement (IHSI) method in a nuclear plant, cooling characteristic with respect to the inner surface of piping is improved by appropriate...
8503599 Optical gamma thermometer  
An optical gamma thermometer includes a metal mass having a temperature proportional to a gamma flux within a core of a nuclear reactor, and an optical fiber cable for measuring the temperature of...
8290111 Electrochemical corrosion potential device and method  
The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical...
7912170 Protection systems for nuclear boiling water reactors  
A protection system for a nuclear boiling water reactor may include a device configured to monitor reactor power; a device configured to monitor reactor pressure; a device configured to determine...
7876872 Reactor power control apparatus of natural circulation reactor and method for controlling reactor power of natural circulation reactor  
In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a reactor pressure vessel which circulates cooling water using the density difference of the...
7818995 Device for measuring back pressure in open-ended chemical reactor tubes  
A device and method for measuring the back pressure in chemical reactor tubes includes many automated features. Inflatable tube seals may be automatically inflated. The device may measure several...
7673496 Device for measuring back pressure in chemical reactor tubes  
A device and method for measuring the back pressure in chemical reactor tubes includes many automated features. Inflatable tube seals may be automatically inflated. The device may measure several...
7634043 Protection systems for and methods of operating nuclear boiling water reactors  
A protection system for a BWR may include a power-dependent high reactor pressure setpoint. The high reactor pressure setpoint that corresponds to at least one value of percent power in an...
7596198 Over temperature and over power delta temperature operating margin recovery method and reactor system employing the same  
A method is provided for recovering operating margin in a nuclear reactor. The reactor includes a steam generator, a Reactor Coolant System (RCS) having a hot leg with a temperature, Thot, and a...
7222058 Method of modeling and sizing a heat exchanger  
A method of modeling a heat exchanger is disclosed and comprises assigning input temperatures, assumed output temperatures, and a set of flow rates, inputting the parameters into a set of...
7139351 Method of and control system for controlling a nuclear reactor outlet temperature  
The invention relates to a control system for controlling an average temperature of a coolant at a reactor core outlet. The control system method detects an average temperature of the coolant at...
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...
6856662 Remote examination of reactor nozzle J-groove welds  
A combined laser and infra red sensing camera is located beneath the reactor head in the vicinity of the closure head tube welds by manipulating known robotic device handling the laser which is...
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...
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...
6493412 Method of calibrating exit thermocouples in a nuclear reactor  
The exit thermocouples of a pressurized water reactor (PWR) are calibrated by recording the thermocouple temperature measurements periodically during power ascension of the reactor together with a...
6435839 Jet pump sensing line clamp assembly and methods  
A clamp assembly for a jet pump sensing line adjacent a jet pump within a nuclear reactor pressure vessel. The jet pump sensing line includes a support block. The clamp assembly includes a clamp...
6252923 In-situ self-powered monitoring of stored spent nuclear fuel  
Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and γ-ray flux and may also...
6249004 Inorganic crystal based composite material high dose dosimeter and method of using same  
The present invention is a composite material containing a mix of dosimeter material powder and a polymer powder wherein the polymer is transparent to the photons of wavelengths absorbed by the...
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...
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...
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...
6061413 Nuclear steam supply temperature measurement system and method  
A temperature measurement system includes, for each of two nuclear steam supply system (NSSS) loops, four temperature sensors each of which provides a value of the temperature of reactor coolant...
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...
5960050 Method of fission heat flux determination from experimental data  
A method is provided for determining the fission heat flux of a prime specimen inserted into a specimen of a test reactor. A pair of thermocouple test specimens are positioned at the same level in...
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...
5761086 Apparatus and method for monitoring pressure-temperature margins  
A real-time parameter margin monitoring system, for a pressurized vessel of an operating nuclear power plant, includes a data acquisition subsystem for acquiring a plurality of real-time...
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...
5712886 Device for detecting and monitoring perforation of the bottom head of the vessel of a nuclear reactor  
The detection device includes at least one thermocouple (10) arranged aligned with the bottom head of the vessel of the nuclear reactor, having a first branch (9) made of a first metallic material...
5684846 Nuclear reactor plant having containment isolation  
A nuclear reactor plant has a nuclear reactor vessel in a containment vessel. Air ducts, sump discharge lines, service water lines and other non-process non-critical lines extending through the...
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...
5652775 Method and device for detecting and monitoring perforation of the vessel bottom head of a nuclear reactor  
The reactor vessel is placed inside a reactor pit having a vertical axis and including a bottom (5) arranged below and aligned with the vessel bottom head. In the event of meltdown of the reactor...
5631937 Method and apparatus for protecting a PWR from departure from nucleate boiling and hot leg boiling  
A pressurized water reactor (PWR) is protected from departure from nucleate boiling and from hot leg boiling by generating a segmented delta temperature trip function having a first line segment...
5619546 Resistance temperature detector nozzle mechanical clamp  
A fluid tight mechanical clamp for creating a compressed graphite seal between a resistance temperature detector nozzle and a NSSS piping hot or cold leg pipe is provided which includes a split...
5615239 Core differential pressure and liquid control line apparatus in a nuclear reactor  
A core differential pressure and liquid control line apparatus for a nuclear reactor is described. The apparatus includes a first portion configured to be positioned within and extend through an...
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...
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...
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...

Matches 1 - 50 out of 301 1 2 3 4 5 6 7 >