A system for simulating maintenance of a reactor core protection system that has at least two or more channels, includes: a simulation signal generation unit for generating a simulation state signal including a normal state or an abnormal state, a communication unit connected to each of the channels of the reactor core protection system to transmit the state signal to the channel, and a control unit for receiving a result signal output from the channel in response to the input simulation state signal and confirming whether the reactor core protection system normally determines a reactor core state by analyzing the result signal.

A system for simulating maintenance of a reactor core protection system that has at least two or more channels, includes: a simulation signal generation unit for generating a simulation state signal including a normal state or an abnormal state, a communication unit connected to each of the channels of the reactor core protection system to transmit the state signal to the channel, and a control unit for receiving a result signal output from the channel in response to the input simulation state signal and confirming whether the reactor core protection system normally determines a reactor core state by analyzing the result signal.

An atomic power plant operation system for assisting the operation of an atomic power generation plant is provided with: an operation monitoring system which monitors and controls the operation of the atomic power generation plant; an abnormality indication monitoring system which, on the basis of an operation history of the atomic power generation plant, monitors an indication of abnormality in the atomic power generation plant; an abnormality diagnosis system which, on the basis of a result of abnormality indication that has been detected, makes an abnormality diagnosis for the atomic power generation plant; and a maintenance system for performing maintenance and management of the atomic power generation plant, wherein the systems are communicably connected, and the abnormality diagnosis system provides the maintenance system with the result of the abnormality diagnosis of the atomic power generation plant.

An atomic power plant operation system for assisting the operation of an atomic power generation plant is provided with: an operation monitoring system which monitors and controls the operation of the atomic power generation plant; an abnormality indication monitoring system which, on the basis of an operation history of the atomic power generation plant, monitors an indication of abnormality in the atomic power generation plant; an abnormality diagnosis system which, on the basis of a result of abnormality indication that has been detected, makes an abnormality diagnosis for the atomic power generation plant; and a maintenance system for performing maintenance and management of the atomic power generation plant, wherein the systems are communicably connected, and the abnormality diagnosis system provides the maintenance system with the result of the abnormality diagnosis of the atomic power generation plant.

A plant maintenance assisting system is provided with: an abnormality indication monitoring system; an abnormality diagnosis system; a maintenance plan creation system; a risk evaluation system; and a component management system. On the basis of risk information and abnormality diagnosis information that is a result of diagnosis by the abnormality diagnosis system, the risk evaluation system determines the need for maintenance work with respect to an abnormality indicating facility. In a case where it is determined that maintenance work with respect to the abnormality indicating facility is necessary, the maintenance plan creation system sets, in a maintenance plan, maintenance implementation timing of maintenance work with respect to a facility including the abnormality indicating facility. On the basis of component management information, the component management system determines whether a component can be procured at the maintenance implementation timing set by the maintenance plan creation system.

An environmentally sequestered nuclear spent fuel pool in one embodiment includes sidewalls and a base slab that confine a water impoundment. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A dual liner system enclosing the pool forms an impervious barrier providing redundant provisions for preventing leakage of contaminated pool water into the environment. An interstitial space is formed between the liners which may be maintained at sub-atmospheric pressures by a vacuum pump system that evacuates the space. By maintaining the pressure in the space at a negative pressure with corresponding boiling point less than the temperature of the pool water, any leakage through the inner-most liner into the interstitial space will vaporize and be extracted via the pump for signaling a potential leak in the liner system.

A process signal control and monitoring system, includes: a signal processing device which is installed on an outside of a nuclear reactor containment vessel, an internal electrical power source, an analog-digital conversion part, an internal communication part which transmits the digital signal to the signal processing device, an internal repeater, and an external repeater which transmits the received signal to a communication satellite. When electric power supply from the signal processing device is disconnected, the internal electrical power source supplies electric power which is charged in the rechargeable battery, to the analog-digital conversion part and the internal communication part; and the internal communication part judges whether communication with the signal processing device is continued or disconnected; and when the communication is judged to be continued, the internal communication part continues transmitting the digital signal to the signal processing device.

A process signal control and monitoring system, includes: a signal processing device which is installed on an outside of a nuclear reactor containment vessel, an internal electrical power source, an analog-digital conversion part, an internal communication part which transmits the digital signal to the signal processing device, an internal repeater, and an external repeater which transmits the received signal to a communication satellite. When electric power supply from the signal processing device is disconnected, the internal electrical power source supplies electric power which is charged in the rechargeable battery, to the analog-digital conversion part and the internal communication part; and the internal communication part judges whether communication with the signal processing device is continued or disconnected; and when the communication is judged to be continued, the internal communication part continues transmitting the digital signal to the signal processing device.

The invention relates to a system for the monitoring and control of the core of a nuclear reactor along which N fission chambers CF.sub.i (i=1, 2, . . . , N) are positioned, N being an integer number greater than or equal to 2, in which: computing means (P) are able to compute a statistical estimation of the n.sup.th order neutron flux .sub.CFi of each fission chamber CF.sub.i and a mean value of estimation of the neutron flux that represents the mean neutron flux prevailing in the core of the nuclear reactor, such that $=\frac{1}{N}\underset{i=1}{\overset{N}{.Math.}}{\mathrm{CFi}}_{}\mathrm{and}$ computing means (M, CMP) are able to compute an ageing indicator (S) for the fission chamber CF.sub.i from the statistical estimation value of the neutron flux .sub.CFi of the fission chamber CF.sub.i.

The invention relates to a system for the monitoring and control of the core of a nuclear reactor along which N fission chambers CF.sub.i (i=1, 2, . . . , N) are positioned, N being an integer number greater than or equal to 2, in which: computing means (P) are able to compute a statistical estimation of the n.sup.th order neutron flux .sub.CFi of each fission chamber CF.sub.i and a mean value of estimation of the neutron flux that represents the mean neutron flux prevailing in the core of the nuclear reactor, such that $=\frac{1}{N}\underset{i=1}{\overset{N}{.Math.}}{\mathrm{CFi}}_{}\mathrm{and}$ computing means (M, CMP) are able to compute an ageing indicator (S) for the fission chamber CF.sub.i from the statistical estimation value of the neutron flux .sub.CFi of the fission chamber CF.sub.i.