G21C17/00

RESISTANCE HEATER ROD AND METHOD OF MAKING

A resistive heater capable of delivering heat loads on the same order as those produced by in-pile nuclear fuel experiments. The heater rod provides the energy for high-temperature steady-state testing, as well as the power needed to simulate the transient pulse in the Transient Reactor Test Loop (TRTL) system. The resistive heater includes a removable housing, two or more thermal conductors in the housing; and one or more stabilizers coupled to the two or more thermal conductors to keep the two or more thermal conductors separated to avoid shorting, wherein the two or more thermal conductors are coupled to the housing via an inert gas (e.g., Helium). The two or more thermal conductors comprise a material with substantially zero infrared spectrum (e.g., sapphire, silica, or glass).

COVARIANCE DATA CREATION APPARATUS, REACTOR CORE ANALYSIS APPARATUS, COVARIANCE DATA CREATION METHOD, MACROSCOPIC COVARIANCE ADJUSTMENT METHOD, REACTOR CORE CHARACTERISTIC EVALUATION METHOD, COVARIANCE DATA CREATION PROGRAM, MACROSCOPIC COVARIANCE ADJUSTMENT PROGRAM, AND REACTOR CORE CHARACTERISTIC EVALUATION PROGRAM

A covariance data creation apparatus configured to execute assembly calculations on a fuel assembly based on microscopic cross sections, the apparatus executing: a perturbation data generation step of deriving a plurality of perturbation quantities of the microscopic cross sections based on microscopic covariance data that is data regarding uncertainties of the microscopic cross sections, and generating microscopic perturbation data from the derived perturbation quantities of the microscopic cross sections; a macroscopic cross section derivation step of executing the assembly calculations based on the microscopic perturbation data generated at the perturbation data generation step, and deriving a plurality of macroscopic cross sections individually corresponding to the perturbation quantities of the microscopic cross sections; and a macroscopic covariance data generation step of generating macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections based on the macroscopic cross sections derived at the macroscopic cross section derivation step.

Abnormality diagnosis system

An abnormality diagnosis system for diagnosing an abnormality event in an atomic power generation plant on the basis of an abnormality indication detection result from an abnormality indication monitoring system is provided with an abnormality diagnosis control unit which acquires a parameter transition in a monitoring period from a non-detection timing to an indication detection timing, and a parameter contribution in the monitoring period and a database. The abnormality diagnosis control unit executes a matching determination between the parameter transition and parameter contribution that have been acquired from the abnormality indication monitoring system, and a parameter transition for determination and a parameter contribution for determination that have been stored in the database, and identifies an abnormality event and an abnormality indication facility that are associated with the parameter transition and parameter contribution determined to be matching.

Abnormality diagnosis system

An abnormality diagnosis system for diagnosing an abnormality event in an atomic power generation plant on the basis of an abnormality indication detection result from an abnormality indication monitoring system is provided with an abnormality diagnosis control unit which acquires a parameter transition in a monitoring period from a non-detection timing to an indication detection timing, and a parameter contribution in the monitoring period and a database. The abnormality diagnosis control unit executes a matching determination between the parameter transition and parameter contribution that have been acquired from the abnormality indication monitoring system, and a parameter transition for determination and a parameter contribution for determination that have been stored in the database, and identifies an abnormality event and an abnormality indication facility that are associated with the parameter transition and parameter contribution determined to be matching.

Systems and methods for providing an integrated power plant advisor

Embodiments of the disclosure can relate to providing an integrated power plant advisor. In one embodiment, a method for providing an integrated power plant advisor can include receiving a signal associated with a failure of a power plant or a power plant component. The method can further include determining one or more root causes associated with the failure of the power plant or the power plant component. Based at least in part on operational data and training data from one or more power plants, a ranking of the one or more root causes associated with the failure of the power plant or the power plant component can be determined. The method can further include outputting the ranking via a client device. Based at least in part on the ranking, a repair or replacement strategy for the power plant or the power plant component can be identified.

Nuclear Reactor Protection Systems and Methods

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

APPARATUS AND METHOD FOR EVALUATING RELIABILITY OF NUCLEAR POWER PLANT OPERATOR
20200342386 · 2020-10-29 ·

In an apparatus for evaluating reliability of a nuclear power plant operator, an expected task finishing time for each task of the operator is calculated based on input data for reliability evaluation of the operator to determine a task completion time for each task of the operator based on the calculated expected task finishing time and the input data. An initial time for the tasks is determined based on the input data and the task completion time for a current task. A total execution time of the operator is calculated based on the determined task completion time and initial time. An available time allowed for the operator to complete the tasks is calculated based on a predetermined allowed time and the determined initial time. A task failure probability is obtained from the difference between the calculated total execution time and the calculated available time based on probability distribution information.

Heat exchanger and nuclear power plant comprising same

The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.

Plant state displaying apparatus, plant state displaying system, and method of displaying plant state

A plant state displaying apparatus displaying information representing a state of a plant includes a generator that: acquires plant information from at least one of devices, apparatuses, and facilities installed in the plant; calculates a state value representing the state of the plant using the plant information; and generates a plant state diagram in which at least one of a color and a density of at least one of devices, apparatuses, and facilities from which the plant information is acquired is changed according to magnitude of the state value; and a display that displays the plant state diagram generated by the generator as the information representing the state of the plant.

Apparatus for use in the inspection of a top grid guide of boiling water reactor

An apparatus for performing an inspection on the beams of the top guide of a BWR includes a housing, an alignment assembly, and an inspection system. The housing is receivable atop the upper edges of a first pair of beams adjacent a receptacle of the top guide. The reception of the housing atop the upper edges of the first pair of beams is facilitated by the alignment assembly which includes a plurality of legs that are simultaneously moved between a retracted position wherein one or more of the legs is disengaged from the beams within the receptacle and an extended position wherein all of the legs are engaged with the beams of the top guide within the receptacle. The inspection system includes a pair of inspection elements that are translated above a second pair of beams that are adjacent the receptacle and that do not have the housing received thereon.