A reactor water radioactivity concentration of a nuclear power plant can be predicted with high accuracy. First, a plant state quantity prediction value is calculated by using a physical model that describes plant state quantities of the power plant including a flow rate of feedwater and a metal corrosion product concentration in feedwater of the reactor water is calculated. Next, data for supervised learning is created, and the data for supervised learning includes the previously calculated plant state quantity prediction value and a plant state quantity such as the flow rate of feedwater, the metal corrosion product concentration in feedwater, a metal corrosion product concentration in reactor water, and a radioactive metal corrosion concentration of the reactor water in the reactor as input data and includes a radioactive metal corrosion concentration in the reactor water which is an actual measured value as output data, and a predictive model is trained.

Systems, methods, apparatuses, and software for computing systems are provided herein. In one example, a system includes processing modules each having a communication interface and a processor, and additional modules each having a communication interface. Communication switch circuitry is coupled to the communication interfaces of the processing modules and the communication interfaces of the additional modules, wherein the communication switch circuitry is configured to establish isolation among ports in the communication switch circuitry for one or more processing modules and one or more additional modules. At least one processor instantiates access to the one or more additional modules for the one or more processing modules over at least the isolation.

A nuclear-power-plant computer-based procedure display device is disposed in a main control room of a nuclear power plant, and includes a operating procedure storage unit that stores a computer-based procedure in which plant operation procedures of the nuclear power plant are divided into procedure steps and listed, a operating procedure display unit that displays the computer-based procedure, and a operating procedure display control unit that controls display of the computer-based procedure. In a case where the procedure step displayed on the operating procedure display unit is selected by an operator, the operating procedure display control unit displays an indication that the procedure step is selected, on the operating procedure display unit.

A method for decommissioning a heavy water reactor facility includes: opening an upper part of the calandria vault; inserting a support device into an inner part of the calandria vault through the upper part of the calandria vault to support the main shell of the calandria; cutting between the main shell and the sub-shell of the calandria by inserting a cutting device into the inner part of the calandria vault through the upper part of the calandria vault; and drawing out the main shell of the calandria to the outside of the calandria vault by moving the support device from the inner part of the calandria vault to the outside through the upper part.

A safety cover structure of a nuclear facility is disclosed. The safety cover structure of a nuclear facility includes: a cover portion rotatably provided over body protection concrete so as to cover a cavity in which a reactor pressure container is positioned; a driving part for providing rotational driving power to the cover part; an opening and closing portion provided at the cover portion and thus products from the cutting and dismantling of the reactor pressure contain move therethrough; a fire extinguishing portion for extinguishing a fire occurring inside the cover portion; a radiation sensor which is provided on the cover portion and which measures radiation dose; and an alarming portion, which receives a sensing signal of the radiation sensor so as to issue an alert when radiation greater than or equal to a predetermined value is discharged from the reactor pressure container.

A nuclear power generation system includes a nuclear reactor that includes a reactor core fuel and a nuclear reactor vessel, the nuclear reactor vessel covering a surrounding of the reactor core fuel, shielding a space in which the reactor core fuel is present, and shielding radioactive rays; a heat conductive portion that is disposed in at least a part of the nuclear reactor vessel to transfer heat inside the nuclear reactor vessel to an outside by solid heat conduction; a heat exchanger that performs heat exchange between the heat conductive portion and a refrigerant; a refrigerant circulation unit that circulates the refrigerant passing through the heat exchanger; a turbine that is rotated by the refrigerant circulated by the refrigerant circulation unit; and a generator that rotates integrally with the turbine.

Disclosed is a process method and system for upfront sampling and characterization to selectively and representatively sample for activation levels of nuclear reactor core irradiated metal alloy internal components using a specialized robust hard metal reactor bit hollow tungsten carbide sampling head in conjunction with bespoke angled sampling gantry. The invention relates to the field of a nuclear reactor metal alloy vacuum hollow sampling head, sampling gantry, and retrieval system. The nuclear-activated metal alloys are drilled and sampled using a TruProBit® metal cutting drill bit. The long hollow drill bit with a hollow metal sampling head traverses the nuclear reactor metal layers and void spaces to cut and retrieve only metal alloy samples. The dry vacuumed airflow picks up the discrete incremental sample of metal filings, chips, and dust produced by the hollow metal cutting edges of the sampling head into a filter and then analyzed for radionuclides of concern.

A method for dismantling a steam generator or heat exchanger, such as found in nuclear power plants, which steam generator or heat exchanger includes a plurality of primary circuit tubes with a contaminated inner surface and wherein one or more tubes are sealed with a plug at both end is provided, the method comprising a) opening one or both ends of each sealed tube by creating an opening in or removing, the plug (13); b) introducing a viscous polymer to cure inside the tube wherein the polymer fills the tube across the full tube cross-section at least at the tube ends, immobilizing contaminations in the filled portion inside the tube (11); c) curing the polymer, then detaching the tubes with cured polymer the detached tubes being sealed by the polymer d) sorting out the detached tubes with polymer.

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.

An underwater decommissioning method of a nuclear facility is disclosed. An underwater decommissioning method of a nuclear facility that includes a nuclear reactor pressure vessel and bio-protective concrete including a cavity in which the nuclear reactor pressure vessel is positioned, includes: (a) floating the nuclear reactor pressure vessel above the cavity; (b) forming an insertion part filled with water in a side spaced apart from the cavity, and installing a support part on a bottom surface of the insertion part; (c) mounting a lower portion of the nuclear reactor pressure vessel on the support part; and (d) repeatedly cutting and decommissioning the nuclear reactor pressure vessel mounted on the support part by using a cutting device in an underwater position.