Abstract: A bearing condition monitoring device is a bearing condition monitoring device for monitoring a condition of a thrust bearing for holding a rotational shaft in a thrust direction. The bearing condition monitoring device includes a first temperature sensor for measuring a temperature of the thrust bearing, and an arithmetic device for counting a frequency at which an evaluation index of a thrust load on the basis of a measurement value by the first temperature sensor exceeds an allowable value, and for outputting an abnormality in the condition of the thrust bearing if the counted frequency exceeds a threshold. The arithmetic device may count, as the frequency, only a case where a state in which the thrust load exceeds an upper limit load continues for not less than a predetermined time.

Abstract: A nuclear reactor includes a vessel (1), a support plate (8), arranged in the vessel (1) above the core (2); a plurality of separate dispensing ducts (21); and support members (33) provided to keep the thermocouple ducts (21) in position. Each support member (33) includes a foot (35) rigidly attached to the support plate (8), a head (37) to which the or each thermocouple duct (21) is attached, and a detachable connection (39) from the head (37) to the foot (35).

Abstract: An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.

Abstract: An in-pipe robot is provided with a rotary actuator 30 that rotates the drilling blade 21 in the circumferential direction of an existing pipe. A wheel body 50 provided with a traveling wheel 52 on both sides and a wheel body 70 provided with a traveling wheel 72 on both sides are supported between side frames 43 of a chassis via pins 54 and 74. The other ends of both the wheel bodies are rotatably coupled around an axle 63 of an intermediate wheel 65 as a pivot. When both the wheel bodies rotate, the intermediate wheels and the rotary actuator move above a horizontal line passing through the pin center. Each pin is disposed at the midpoint of a line connecting the center of the traveling wheel and the center of the intermediate wheel so that the rotation axis v1 of the rotary actuator coincides with the pipe center axis of the existing pipe.

Abstract: A nuclear system. The nuclear system includes a fuel rod for use in a nuclear reactor. The fuel rod includes a cladding comprising an interior region, unspent fuel pellets housed in the interior region of the cladding, and a resonant electrical circuit supported within the interior region of the cladding. The resonant electrical circuit is configured to receive an excitation pulse through the cladding, and responsive to the received excitation pulse, generate a response pulse in the form of a magnetic field signal that is structured to travel wirelessly from the interior region and through the cladding. The nuclear system also includes a receiver positioned outside of the cladding and within the nuclear reactor. The receiver is configured to receive the response pulse and generate an output based on the received response pulse.

Abstract: A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.

Abstract: A method for detecting the thicknesses of coating layers of nuclear fuel particles, comprising: collecting a surface image of a sample to be tested under a first amplification factor (S310); determining a testable particle in the surface image (S320); collecting a cross section image of the testable particle under a second amplification factor, wherein the second amplification factor is greater than the first amplification factor (S330); and determining the center of the testable particle in the cross section image and profile lines of all coating layers, and determining the thickness of each coating layer according to the center and the profile lines of each coating layer (S340). Also provided is a device for detecting the thicknesses of coating layers of the nuclear fuel particles.

Abstract: Methods and systems for assessing, detecting, and responding to malfunctions involving components of autonomous vehicles and/or smart homes are described herein. Malfunctions may be detected by receiving sensor data from a plurality of sensors. One of these sensors may be selected for assessment. An electronic device may obtain from the selected sensor a set of signals. When the set of signals includes signals that are outside of a determined range of signals associated with proper functioning for the selected sensor, it may be determined that the selected sensor is malfunctioning. In response, an action may be performed to resolve the malfunction and/or mitigate consequences of the malfunction.

Abstract: A flow sensor sub-assembly for sensing flow of a fluidic medicament includes a flow tube having a flow tube inlet and a flow tube outlet, and an acoustical transmission rate. The medicament flows through the flow tube. A first piezo element is arranged at an upstream position of the flow tube and a second piezo element is arranged at a downstream position of the flow tube, such that the first piezo element and the second piezo element are mounted apart a pre-selected distance from each other. An absorber sheath encircles the flow tube. The absorber sheath has an upstream end and a downstream end. The absorber sheath is comprised of a material with an acoustical transmission rate different than the flow tube.

Abstract: A method and system for localizing faults in an industrial process is proposed. The industrial process includes a plurality of components. The method includes receiving structural plant data from an industrial plant. A structured model of the process is generated from the structural plant data. Sensor data measuring characteristics of the plurality of components is also received. Parameters of the structured model are identified from the received sensor data and stored. Faults are detected during operation of the industrial plant utilizing the identified parameters and detecting changes in the parameters by comparing current parameters to stored parameters. The fault information is then displayed via a display to an operator.

Abstract: A modular analysis engine provided classification of variables and data in an industrial automation environment. The module may be instantiated upon receipt of an input data structure, such as containing annotated data for any desired variables related to the machine or process monitored and/or controlled. The data may be provided in a batch or the engine may operate on streaming data. The output of the module may be a data structure that can be used by other modules, such as for modeling, optimization, and control. The classification may allow for insightful analysis, such as for textual classification of alarms provided in the automation setting.

Abstract: A system for externally cooling a radiation shielded cask containing heat-emitting high level radioactive waste such as spent nuclear fuel. The system includes the cask defining an internal cavity configured to hold an unshielded canister containing the spent nuclear fuel. An annular cooling water header extends circumferentially around the entire circumference of the cylindrical sidewall of the cask. The header comprises plural dispensing outlets which direct cooling water onto the cask, thereby wetting the entire sidewall of the cask. The cooling water provides an external heat sink for absorbing the heat emitted through the external wall surface of the cask generated by the spent nuclear fuel. In various embodiments, the cooling water header may have a continuous annular structure, or be formed by two or more header segments. The header may be supported directly from the cask by detachably mounted brackets.

Abstract: A method of determining if a circuit interrupter operating mechanism has an acceptable trip margin includes determining a model trip margin, providing a circuit interrupter, the circuit interrupter disposed in situ, the circuit interrupter including an operating mechanism, determining a circuit interrupter trip margin by: providing an internal sensor assembly, the internal trip margin sensor assembly structured to record trip margin data, providing a transfer function module, providing a computer structured to execute the transfer function module, executing the transfer function module on the computer, utilizing the trip margin sensor assembly to generate trip margin data, transmitting the trip margin data to the transfer function module, processing the trip margin data to generate a trip margin, and determining if the trip margin is acceptable relative to the model trip margin.

Abstract: A repeating setpoint generator module selectively varies a setpoint for an output parameter according to a predetermined pattern that repeats during successive time intervals. A closed-loop module, during a first one of the time intervals, generates N closed-loop values based on N differences between (i) N values of the setpoint at N times during the first one of the time intervals and (ii) N measurements of the output parameter at the N times during the first one of the time intervals, respectively. An adjusting module, during the first one of the time intervals, generates N adjustment values based on N differences between (i) N values of the setpoint at the N times during a second one of the time intervals and (ii) N measurements of the output parameter at the N times during the second one of the time intervals, respectively.

Abstract: Disclosed are a method and apparatus for making a radioisotope and a composition of matter including the radioisotope. The radioisotope is made by exposing a material to neutrons from a portable neutron source.

Abstract: A device for detecting a contaminant on a scaffolding pole. The device includes an outer detector for detecting a contaminant on an outer surface and an inner detector for detecting a contaminant on an inner surface. The device also includes a mechanism for transporting a scaffolding pole through the device, past the detectors. A contaminant is detected on the outer and inner surfaces of the scaffolding pole using the outer and inner detectors respectively.

Abstract: A radionuclide generation system including a tube system configured to permit insertion and removal of irradiation targets into an instrumentation finger of a nuclear reactor, and an irradiation target drive system configured to insert the irradiation targets into the instrumentation finger and to remove the irradiation targets from the instrumentation finger. The radionuclide generation system further includes an instrumentation and control unit which is linked to an online core monitoring system and being configured to calculate optimal irradiation locations for the irradiation targets based on the actual state of the reactor as provided by the online core monitoring system.

Abstract: An object recognition system using an ultrasonic sensor is proposed, the system including an amplifier amplifying an output of the ultrasonic sensor; an analog-to-digital converter converting an output of the amplifier into a digital signal; and a feature point extractor extracting feature points using an output of the analog-to-digital converter; and an object recognizer recognizing the object by using the feature points extracted from the feature point extractor.

Abstract: A trip avoidance X-ray inspection system, typically defining a specialized system that delivers pulsed X-rays, comprises one or more pulse X-ray cameras, each comprising a known set of effects on nucleonic instrumentation; a predetermined set of such shielded X-ray sources; a predetermined set of nucleonic instrumentation operatively in communication with one or more pulse X-ray cameras; and a digital radiography detector adapted to allow, process, or otherwise create an X-ray produced image when disposed proximate predetermined set of nucleonic instrumentation. The pulse X-ray camera is adapted to be disposed at a predetermined distance from predetermined set of shielded X-ray sources.

Abstract: A device and method for inspecting and measuring weld defects in a cylindrical wall of a cylindrical conduit. The device can include an inspection head forming a probe having a proximal end and a distal end along its longitudinal axis, and of which a first side called “inner side” is provided with at least one ultrasound wave transducer. The inspection head can include a second side, called “outer side” opposite the first side that has a curved surface in the form of a cylinder fraction, and wherein the curved surface of the second side has outward facing convexity. The wave transducer can be formed of a series of juxtaposed elements, each element being both a transmitter and receiver, wherein a surface of the series is curved and in the form of a cylinder fraction, and wherein the surface of the series has outward facing concavity.

Abstract: The present invention relates to a liquid mixing device which has a control system and electronic regulation, in charge of receiving the parameters set with respect to the liquid which is expected to be supplied by the tap or supply means whereto said device is connected and which acts on the regulation means of the different supply lines of liquids to mix to achieve said parameters, which has a high measurement and actuation dynamic thanks to measuring sections with ultrasonic transducers and proportional solenoid valves and a configuration and geometry of said measuring sections which allows having a multitude of reliable measurements per second.

Abstract: Methods of and systems to provide performance measurement are provided utilizing an architecture configured to efficiently merge and monitor different types of performance data. Connectors are provided to receive and translate different types of performance data from different sources. The performance data is translated into and stored in a common data model format. In some embodiments, key attributes are defined for each of the performance data sources that uniquely characterizes each relevant performance data so that is can be parsed into separate processing streams to increase system performance. The key attributes also act as cues to organize the performance data as it is being merged so that it can be accessed without requiring a specific source data linkage. Using model listeners, determinations can be quickly made regarding when performance data is changed to reduce calculations necessary to determine measure values. Some embodiments merge different types of performance data in real-time.

Abstract: Methods, systems, and apparatus, including computer programs encoded on computer storage media, for blockchain-based storage of patrol inspection proof are provided. One of the methods includes: receiving proof information of patrol inspection at a patrol inspection site; obtaining one or more operating environment parameters of the mobile terminal at a time of the patrol inspection, wherein the one or more operating environment parameters comprise at least location information and sensor data of the mobile terminal; performing credibility verification on the patrol inspection site based on the proof information, the location information, and the sensor data using an algorithm model based on labeled identification information, labeled operating environment parameters, and historical attendance information; and in response to the credibility verification being successful, uploading verification information associated with the proof information for storing in a blockchain.

Abstract: This invention is directed to an automatic inspection system of welding spots in the car body and a control method thereof, the automatic inspection system comprising a controller and a robot arm, a probe device, and a visual system, wherein the robotic arm holds a camera and the probe device, the probe device targets at car body welding spot and form the first included angle with the camera. Many lighting sources are distributed around the camera, which form the second included angle with the camera. The camera is connected with Image Collecting and Processing Device to obtain position data of welding spot in the car body, the controller is connected with Image Collecting and Processing Device by network, and foresaid controller rectifies position of the probe on the robotic arm according to the position of welding spot in the car body.

Abstract: A bearing lubrication system includes a lubricant distributor configured to perform a lubrication operation by moving lubricant toward an interior of a housing of a bearing, at least one sensor configured to measure at least one condition of the bearing and to produce a signal indicative of the at least one measured condition and a controller configured to produce a transient detection signal, a signal indicative of a second derivative of the measurement signal, for example, and to determine whether an absolute value of the transient detection signal exceeds a threshold value during a given time period after the lubrication operation and to output a failure signal indicative of a lubrication failure in response to a determination that the absolute value of the transient detection signal does not exceed the threshold value during the given time period. Also a method of operating a bearing lubrication system.

Abstract: A method and system for measuring vertical wheel impact force in real-time based on tire pressure monitoring is provided by the present invention. The system mainly includes the four modules, namely a tire pressure derotation preprocessing, a tire pressure-wheel force system identification, a calibration method, and an integrated device for tire pressure-wheel force measurement. The method uses the integrated device to collect tire pressure data in real-time. The corresponding vertical wheel impact force is obtained through the derotation preprocessing and the tire pressure-wheel force system identification, and is calibrated according to the calibration method. The present invention provides an efficient, accurate, and highly adaptable wheel force measurement solution in the theoretical aspect and device aspect, which meets the requirements for the quick evaluation of the bridge health condition.

Abstract: Systems and methods for a product driven approach to technology provisioning, operations, and billing are provided. Some embodiments provide an Information Technology (IT) business architecture built around the product driven methodology. This architecture can be designed to optimize the demand side provisioning of technology products to meet business intent and the execution of supply side assembly and implementation lifecycle. A technology model can be used that recursively decomposes services and products into various components. As a result, the technology model allows for effective and efficient provisioning, pricing, and impact assessment of the organization's technology to thereby drive the efficiency of scale and the automation of the provisioning, the finance, and the operation businesses.

Abstract: A repeating setpoint generator module selectively varies a setpoint for an output parameter according to a predetermined pattern that repeats during successive time intervals. A closed-loop module, during a first one of the time intervals, generates N closed-loop values based on N differences between (i) N values of the setpoint at N times during the first one of the time intervals and (ii) N measurements of the output parameter at the N times during the first one of the time intervals, respectively. An adjusting module, during the first one of the time intervals, generates N adjustment values based on N differences between (i) N values of the setpoint at the N times during a second one of the time intervals and (ii) N measurements of the output parameter at the N times during the second one of the time intervals, respectively.

Abstract: There is provided an inspection device for inspecting an inner surface of a nozzle provided in a reactor vessel. The inspection device includes: a device frame, an inspection unit provided on the device frame, an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the inner surface of the nozzle, a rotation moving mechanism for rotating and moving the inspection unit, a calibration test unit arranged on the device frame for calibrating the inspection unit; and a calibration test unit forward/backward moving mechanism for moving the calibration test unit forward or backward in the direction along the central axis with regard to a track where the inspection unit makes push-out movement.

Abstract: An improved testing and data gathering method is described herein with reference to testing a new fuel, as an exemplary component to be tested for licensure purposes. The method includes generally: generating models for the new system; making samples and getting them accepted for a reactor; and testing the samples in a test or commercial reactor until the exposure time is reached for the expected cycle length of the fuel at final use. The method is preferably done concurrent to submitting a license application for commercial use of the new component to the relevant government body to expedite license testing review.

Abstract: A sample container, sampling system and operating methods permit representative sampling from a liquid phase or boiling liquid, a gaseous phase, a containment sump, containment atmosphere, or condensation chamber of a nuclear power plant following a severe accident. A sample container obtaining an environmental sample includes an outer chamber surrounded by an outer container wall, being directly fluidically connected to the environment through a passage opening in the outer container wall and being fillable with a liquid at least in a base region. An inner chamber surrounded by an inner container wall is fluidically connected to the base region through a passage opening in the inner container wall, has connections for sampling and conveyor medium lines and is otherwise pressure and media tightly sealed from the environment. A pneumatically or hydraulically actuatable closure device for the passage opening between the outer and inner chambers has an actuation medium line connection.

Abstract: A transmitter device includes a neutron detector structured to detect neutron flux, a capacitor electrically connected in parallel with the neutron detector, a gas discharge tube having an input end and an output end, and an antenna electrically connected to the output end. The input end is electrically connected with the capacitor. The antenna is structured to emit a signal corresponding to the neutron flux.

Abstract: A detection apparatus is usable to detect the neutron absorption capability of a control element of a nuclear installation and includes a neutron radiograph apparatus and a robot apparatus. The neutron radiograph apparatus includes a neutron emission source of variable strength, a detector array, a mask apparatus and a positioning robot all under the control of a central processor and data acquisition unit. The neutron emission source is advantageously switchable between an ON state and OFF state with variable source strength in the ON state, which avoids any need for shielding beyond placing the neutron emission source in an inspection pool at the nuclear plant site including but not limited to the spent fuel or shipping cask laydown pools. The neutron emission source is situated at one side of a wing of the control element and generates a neutron stream, the detector array is situated on an opposite side of a wing, and the neutron emission source and detector array are robotically advanced along the wing.

Abstract: An ultrasonic phased array transducer assembly having a single housing in which a plurality of phased array transducer subassemblies are mounted at a skewed angle relative to a leading face of the housing and to each other, with each transducer mounted on composite wedge(s) at different orientations within the housing.

Abstract: A vehicle periphery monitoring device includes a location information acquisition unit configured to acquire a current location of the vehicle; a vehicle-mounted camera configured to capture an image of the exterior of the vehicle; a display device configured to display the image; a caution point information storage unit configured to store information relating to a caution point, which is a location where use of the vehicle-mounted camera is recommended; and a control unit configured to carry out vehicle exterior image display to output the image acquired by the vehicle-mounted camera to the display device, wherein the control unit carries out the vehicle exterior image display when it is determined that the caution point is present near the acquired current location.

Abstract: A fuel ball detecting method and system with a self-diagnosis function are provided. The method includes: exciting a first detecting coil and a second detecting coil of a fuel ball sensor disposed outside a pipeline; obtaining a first voltage signal U1 from the first detecting coil and a second voltage signal U2 from the second detecting coil; processing U1 and U2 by differential amplification, band pass filtering, phase sensitive detection and low pass filtering by a signal processor to obtain a fuel ball waveform signal U0; determining whether the fuel ball passes the pipeline according to U0 by a single chip microcomputer; determining whether the first and the second detecting coils, the signal processor and the single chip microcomputer work normally; outputting a result showing whether the fuel ball passes the pipeline, when the first and the second detecting coils, the signal processor and the single chip microcomputer work normally.

Abstract: An autonomous device for detecting characteristics of a medium to be measured is disclosed. The device includes a sensor, a first microcontroller and a second microcontroller. The first microcontroller has a memory which is not resistant against gamma radiation during the sterilization of the device and the second microcontroller has a memory which is resistant against gamma radiation during the sterilization of the device.

Abstract: A technique may be employed to facilitate manufacturing/processing of generator tubes for use in a variety of logging applications. A getter-based gas storage chamber is provided with a getter able to adsorb a desired gas such as a deuterium and/or tritium gas. The getter-based gas storage chamber may be connected with a neutron tube via a gas flow network and a releasable coupling. The gas, e.g. deuterium and/or tritium gas, is released by heating the getter. The gas is allowed to flow through the gas flow network and into the neutron tube.

Abstract: A system has an actuator with a first surface and a second surface, the first surface being offset a step dimension from the second surface. A sensor is configured to measure a distance between the sensor and both the first surface and the second surface via a signal received by the sensor after having reflected off the first surface or the second surface. The step dimension is greater than a minimum dimension, which is defined in view of a medium through which the actuator moves and a frequency of the signal.

Abstract: A method for simulating the fluid flow in a vessel of a nuclear reactor is provided. The reactor includes a core inside the vessel, the core including a lower plate, an upper plate and fuel assemblies extending between the plates, and having a volume axially delimited by first and second interfaces corresponding to the plates. The method includes computing, for the core volume, the fluid pressure and speed, from an initial value of the speed or pressure in the first interface and respectively in the second interface, and using the fluid mass, movement quantity and energy balance equations.

Abstract: An inspection apparatus may include an installation platform and a scan head. The scan head may be configured to engage in an index movement, a theta movement, a wrist fold movement, and a scan movement. During the scan movement, a transducer of the scan head travels a circumferential path so as to allow an inspection of a surface that is opposite of a surface on which the installation platform is mounted. The inspection apparatus may be used to inspect a reactor component in a nuclear reactor.

Abstract: Provided are a neutron detector for detecting a neutron flux distribution of the inside of a reactor, a drive cable connected to the neutron detector, a drive unit for driving the drive cable, a plurality of guide thimbles provided being inserted from the outside of the reactor into the reactor, for inserting the neutron detector, a storage tube for storing the neutron detector, a path transfer device connected to the drive unit, for selecting one of insertion of the neutron detector into each of the guide thimbles and insertion of the neutron detector into the storage tube, and an inspection guide tube connecting the drive unit and the storage tube. The drive unit has a switching unit for switching between the path transfer device side and the inspection guide tube side.

Abstract: A repeating setpoint generator module selectively varies a setpoint for an output parameter according to a predetermined pattern that repeats during successive time intervals. A closed-loop module, during a first one of the time intervals, generates N closed-loop values based on N differences between (i) N values of the setpoint at N times during the first one of the time intervals and (ii) N measurements of the output parameter at the N times during the first one of the time intervals, respectively. An adjusting module, during the first one of the time intervals, generates N adjustment values based on N differences between (i) N values of the setpoint at the N times during a second one of the time intervals and (ii) N measurements of the output parameter at the N times during the second one of the time intervals, respectively.

Abstract: An animal trap comprising a trap (106, 102, 302) section having at least one moveable wall section (136, 228, 314), being moveable with respect to one or more other walls of the trap section to thereby alter the size of the trap section; animal detection means (138, 242, 306) operable to detect the presence of an animal within the trap section and adapted to signal such a presence to control means, which control means is operable, upon receipt of said signal, to cause movement of the moveable wall section (136, 228, 314) and thus alter the size of the trap section.

Abstract: A method for controlling the positions of a plurality of nuclear fuel assemblies (1) relative to an upper core plate (3) in a nuclear reactor core, the method including the following steps: choosing a reference point (13) in internals or in a reactor vessel; determining the positions of S-shaped holes of the nuclear fuel assemblies (1) relative to the reference point (13), each S-shaped hole being intended to cooperate with a corresponding centering pin of the upper core plate (3); acquiring the positions of the centering pins of the upper core plate (3) relative to the reference point (13); and comparing the positions of the S-shaped holes and the positions of the pins and deducing therefrom whether the nuclear fuel assemblies (1) are correctly positioned relative to the upper core plate (3).

Abstract: A method involving periodic implementation, during the same operating cycle of the reactor, the method including following steps of: a) calculating, from measurements provided by sensors present in the reactor, the three-dimensional distribution of the local power in the core, b) simulating at least one accidental transient occurrence of power applied to the calculated three-dimensional distribution of local power, c) identifying, using thermomechanical calculations, at least one rod which is the most likely to be subject to a fracture of the cladding thereof during the simulated transient occurrence of power, and d) determining, using thermomechanical calculations on the rod identified, the value of the parameter which is representative of the operability of the reactor.

Abstract: The present invention relates to a torsional vibration resonance frequency measuring method and a novel amplitude transformer for assessing the stability of dental implants. In one example, a torsional vibration resonance frequency measuring method includes installing an amplitude transformer on a dental implant, energizing a torsional vibration mode, gathering resonance signals, and analyzing a resonance frequency. In another example, an amplitude transformer for measuring torsional vibration resonance frequency in a dental implant, includes an anti-rotary horizontal double-winged component and a central bolt. The central bolt is configured to closely connect with the inner threads of the dental implant, such that the amplitude transformer can integrate with the dental implant sufficient to vibrate as an integral structure under energizing.

Abstract: A system for monitoring a condition of a nuclear reactor pressure vessel disposed in a radioactive environment includes an instrument structured to monitor a condition of the nuclear reactor pressure vessel; a powered wireless transmitting modem disposed in the radioactive environment, the wireless transmitting modem being electrically coupled to the instrument; a receiving modem disposed in the line of sight of the transmitting modem, the receiving modem being in wireless communication with the transmitting modem; and a signal processing unit electrically coupled to the receiving modem, the signal processing unit being structured to determine the condition of the nuclear reactor pressure vessel from the instrument. The transmitting modem is powered by a thermocouple disposed in or on the reactor pressure vessel.

Abstract: A method for monitoring a transmitter (1) with a measurement (2) and a transmission unit (3), with which a measurement (2) signal is generated that is dependent on a measurement quantity, and with the transmission unit (3) receiving the measurement signal, and based on the measurement signal, an output signal is transferred to a signal transmission element (4). To makes it possible to recognize an error, an input signal is taken from the signal transmission element (4) and is transferred to the measurement unit (2) as a comparison signal which corresponds to the input is compared with a stored signal and based upon the outcome of the comparison, either the measurement signal is transferred from the measurement unit (2) to the transmission unit (3) or the transmission unit (3) is shifted into a definable state and an error signal is transferred to it.

Abstract: A nuclear power plant control system including: a detection unit for detecting a specific event occurring in the nuclear power plant; an on-site equipment handling the event; and a majority decision judging device and an on-site equipment control device which constitute a plurality of control devices respectively operating independently. Each of the control devices includes a plurality of arithmetic units which perform arithmetic processes independently and in parallel based on a detection result of the detection unit, and output a signal for controlling the on-site equipment according to the results of operations of the arithmetic processes. The plurality of arithmetic units perform a matching process for harmonizing process statuses of the arithmetic processes of respective arithmetic units with each other when starting up the control devices, and after completing the matching process, respectively perform the arithmetic processes independently and in parallel.