The present invention relates to a screen sharing system of a nuclear power plant main control room for improving operation safety of a power plant. According to an example of the present invention, a power plant control screen of each operator is shared in real-time among other operators by a simple manipulation such that operators can easily simultaneously check a power plant operation screen of other operators, whereby a mistake of another operator can be detected and manipulated in time, thus improving operation safety of a power plant.

The present invention relates to a screen sharing system of a nuclear power plant main control room for improving operation safety of a power plant. According to an example of the present invention, a power plant control screen of each operator is shared in real-time among other operators by a simple manipulation such that operators can easily simultaneously check a power plant operation screen of other operators, whereby a mistake of another operator can be detected and manipulated in time, thus improving operation safety of a power plant.

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.

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.

A submersible system and method for measuring the gas volume fraction in an aerated fluid inside a reactor (1) wherein the aerated fluid comprises a gas dispersed in the form of bubbles in a fluid in the form of a solution, suspension, mixture of liquids or a combination thereof. The submersible system comprises: an open and pass-through gas exclusion device (20) of a variable cross section wherein the inlet opening whereby the fluid enters without gas bubbles towards the opened and through gas bubbles exclusion device (20) is greater than the outlet opening whereby the fluid exits without gas bubbles of the opened and through gas bubble exclusion device (20). The outlet opening abuts with an inlet pipe (23). A chamber (24) which can provide a sealed camera, can contain at least one flow meter to measure the gas-free fluid velocity when circulating between an inlet (27) and an outlet (28) of the chamber (24) or sealed camera The inlet (27) of the chamber (24) or sealed camera can be coupled to the inlet pipe (23). The outlet (28) of the chamber (24) or sealed camera can be coupled to an outlet pipe (26) of the liquid dispersion towards the reactor (1). A flow transmitter (29) connected to the flow meter, located inside or outside said chamber (24) or sealed camera, generates an outlet signal proportional to the bubbles-free fluid velocity through a gas bubble exclusion device and a calculation unit (30) which generates an output signal (31) proportional to the gas volume fraction in the aerated fluid.

A method for determining whether to perform maintenance for an electronic device includes generating a baseline characterization of thermal performance for a heat-generating component of the electronic device at a baseline date. The method also includes generating an assessment characterization of the thermal performance at an assessment date after the baseline date. The method further includes generating a historical trend that includes the baseline characterization and the assessment characterization. Additionally, the method includes determining whether to perform maintenance for the heat-generating component based on the historical trend and a specified maintenance parameter.

A power sensor system for monitoring a subcritical neutron generator is provided. The power sensor system comprises a self-powered sensor insert. The self-powered sensor insert comprises an insert thimble and a detector assembly. The insert thimble includes an outer housing, a power generator configured to produce an electrical power based on an incident radiation and a first electrical interface electrically connected to the power generator. The detector assembly includes a solid state radiation detector able to provide a detector signal directly proportional to a neutron flux level, a transmitter configured to wirelessly output a transmitter signal based on the detector signal and a second electrical interface configured to electrically couple to the first electrical interface. A power monitor system comprising a power sensor system and a control system and a method for optimizing a subcritical neutron generator are also provided.

An assembly for containing and detecting leaks from a coolant line includes a basin with side and end walls, and at least one U-shaped cavity in an end wall for receiving a coolant line of a liquid cooling system. A bottom of the basin includes at least one sloped interior surface arranged to divert water in the basin to a local low point, where a sensor is positioned and operable to detect liquid in the collection basin. A leak detection system can employ a leak detection assembly to detect and/or locate a leak.

A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.

A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.