Provided is an apparatus for evaluating a response time of a plant protection system. The apparatus includes: a classification module classifying a design process related to a response time requirement of each channel performing a safety function into four operations of a safety analysis operation, a system design operation, a response time analysis operation, and a response time test operation; and an integrated evaluation module determining whether a response time evaluation is proper based on a time t1 derived in the safety analysis operation, a time t2 derived in the system design operation, a time t3 derived in the response time analysis operation, and a time t4 derived in the response time test operation.

Provided is an apparatus for evaluating a response time of a plant protection system. The apparatus includes: a classification module classifying a design process related to a response time requirement of each channel performing a safety function into four operations of a safety analysis operation, a system design operation, a response time analysis operation, and a response time test operation; and an integrated evaluation module determining whether a response time evaluation is proper based on a time t1 derived in the safety analysis operation, a time t2 derived in the system design operation, a time t3 derived in the response time analysis operation, and a time t4 derived in the response time test operation.

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.

One variation of a method for deploying a nuclear reactor system includes: constructing a tunnel at a particular location; and installing the nuclear reactor, loaded with a first core assembly, within the tunnel. The method further includes, during an operating period: in response to detecting a high-energy demand period: triggering operation of the nuclear reactor at a first capacity, directing a first portion of energy output to a charging station for charging electric vehicles, and directing a second portion, less than the first portion, of energy output to a gas sequestration subsystem; and, in response to detecting a low-energy demand period, triggering operation of the nuclear reactor at a second capacity less than the first capacity, directing a third portion of energy, less than the first portion, output to the charging station, and directing a fourth portion of energy, exceeding the second portion, output to the gas sequestration subsystem.

One variation of a method for deploying a nuclear reactor system includes: constructing a tunnel at a particular location; and installing the nuclear reactor, loaded with a first core assembly, within the tunnel. The method further includes, during an operating period: in response to detecting a high-energy demand period: triggering operation of the nuclear reactor at a first capacity, directing a first portion of energy output to a charging station for charging electric vehicles, and directing a second portion, less than the first portion, of energy output to a gas sequestration subsystem; and, in response to detecting a low-energy demand period, triggering operation of the nuclear reactor at a second capacity less than the first capacity, directing a third portion of energy, less than the first portion, output to the charging station, and directing a fourth portion of energy, exceeding the second portion, output to the gas sequestration subsystem.

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.

Disclosed is a diagnostic apparatus structured to be electrically connected with a coil stack of a drive mechanism of a control device of a nuclear reactor. The coil stack has a plurality of coils. The diagnostic apparatus includes a power supply and a controller including a processor and a memory that stores a number of routines including a number of instructions. When executed on the processor the instructions cause the diagnostic apparatus to apply to a coil a voltage that varies as a function of time, detect a current in the coil as a function of time, identify in the current a first inflection point and a second inflection point, and determine, based upon an electronic evaluation that includes the first inflection point and the second inflection point, that the coil is one of functioning properly and in a state of at least partial failure.

Disclosed is a diagnostic apparatus structured to be electrically connected with a coil stack of a drive mechanism of a control device of a nuclear reactor. The coil stack has a plurality of coils. The diagnostic apparatus includes a power supply and a controller including a processor and a memory that stores a number of routines including a number of instructions. When executed on the processor the instructions cause the diagnostic apparatus to apply to a coil a voltage that varies as a function of time, detect a current in the coil as a function of time, identify in the current a first inflection point and a second inflection point, and determine, based upon an electronic evaluation that includes the first inflection point and the second inflection point, that the coil is one of functioning properly and in a state of at least partial failure.

A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.