A system includes: a monitoring data obtainer configured to obtain real-time monitoring data regarding equipment; a deterioration index calculator configured to calculate an estimated deterioration index of the equipment from an equipment model and the obtained monitoring data, the equipment model being created by modeling a relationship between the real-time monitoring data of the equipment in a normal state; a time change predictor configured to predict a time change of the estimated deterioration index; and a scheduler configured to estimate a cost in a future caused by the abnormal event, the cost being estimated based on the predicted time change of the estimated deterioration index and the relationship between the estimated deterioration index and the probability of the abnormal event.

An experimental system a method for studying jet impact characteristics at a core outlet of a fast reactor are provided. The system includes a jet impact main loop including a water storage tank, plunger pumps, a filter, preheaters, a jet impact chamber, a heat regenerator, a condenser, valves, flow meters and pipelines connecting these facilities; a cooling loop including cooling tower, a cooling pump, a regulating valve and a flow meter; and a makeup water loop including a deionized water machine, a makeup water tank and a plunger pump. Water in the water storage tank flows to the heat regenerator via the plunger pump, is preliminarily heated by the heat regenerator and then is divided into three branches to flow to the jet impact container.

A plant abnormality predict detection system for detectably monitoring an indication of abnormality in an atomic power generation plant is provided with: a data storage unit which stores plant operation data including an instrument parameter measured in the atomic power generation plant; and a monitoring and control unit which, on the basis of the plant operation data, detects an indication of abnormality in the atomic power generation plant, wherein the atomic power generation plant performs a base-load operation so that the instrument parameter has a prescribed target value, and wherein the monitoring and control unit, on the basis of past plant operation data, sets a normal range W that is a range in which the instrument parameter at the current time transitions normally, and detects an indication of abnormality when the instrument parameter at the current time exceeds the normal range W that has been set.

A plant abnormality predict detection system for detectably monitoring an indication of abnormality in an atomic power generation plant is provided with: a data storage unit which stores plant operation data including an instrument parameter measured in the atomic power generation plant; and a monitoring and control unit which, on the basis of the plant operation data, detects an indication of abnormality in the atomic power generation plant, wherein the atomic power generation plant performs a base-load operation so that the instrument parameter has a prescribed target value, and wherein the monitoring and control unit, on the basis of past plant operation data, sets a normal range W that is a range in which the instrument parameter at the current time transitions normally, and detects an indication of abnormality when the instrument parameter at the current time exceeds the normal range W that has been set.

Disclosed are a method and device for evaluating damage caused by secondary stress to a vacuum vessel, a terminal device, and a medium, to perform following steps: obtaining secondary stress of a vacuum vessel that passes a primary-stress failure evaluation; obtaining structural damage parameters of the vacuum vessel when determining, based on evaluation parameters for the primary-stress failure evaluation of the vacuum vessel and the obtained secondary stress, that the vacuum vessel meets a precondition for a progressive deformation; and determining, based on the obtained structural damage parameters, whether the vacuum vessel meeting the precondition for the progressive deformation experiences structural damage due to the progressive deformation. In this way, a vacuum vessel of a nuclear fusion reactor can be evaluated based on damage caused by the secondary stress.

Disclosed are a method and device for evaluating damage caused by secondary stress to a vacuum vessel, a terminal device, and a medium, to perform following steps: obtaining secondary stress of a vacuum vessel that passes a primary-stress failure evaluation; obtaining structural damage parameters of the vacuum vessel when determining, based on evaluation parameters for the primary-stress failure evaluation of the vacuum vessel and the obtained secondary stress, that the vacuum vessel meets a precondition for a progressive deformation; and determining, based on the obtained structural damage parameters, whether the vacuum vessel meeting the precondition for the progressive deformation experiences structural damage due to the progressive deformation. In this way, a vacuum vessel of a nuclear fusion reactor can be evaluated based on damage caused by the secondary stress.

A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.

A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.

A measurement core for measuring nuclear heating, the core extending in a longitudinal direction and having a main plane, includes at least: a first layer of material, forming a first sample; a first thin layer of electrical insulation on the first sample; a thin conductive layer forming a heating electrical resistor on the first layer of electrical insulation; and a second thin layer of electrical insulation on the heating electrical resistor. A calorimetric sensor includes: an outer jacket; a gas contained in the jacket; a measurement core disposed in the jacket; a link for holding the core in the jacket and transferring the heat between the core and the jacket; and temperature measurement capable of measuring the temperature at a hot point, and the temperature at a cold point.

A measurement core for measuring nuclear heating, the core extending in a longitudinal direction and having a main plane, includes at least: a first layer of material, forming a first sample; a first thin layer of electrical insulation on the first sample; a thin conductive layer forming a heating electrical resistor on the first layer of electrical insulation; and a second thin layer of electrical insulation on the heating electrical resistor. A calorimetric sensor includes: an outer jacket; a gas contained in the jacket; a measurement core disposed in the jacket; a link for holding the core in the jacket and transferring the heat between the core and the jacket; and temperature measurement capable of measuring the temperature at a hot point, and the temperature at a cold point.