A configurable unit cell of a core of a nuclear reactor is disclosed herein. The configurable unit cell includes a core block material and a plurality of interchangeable components configured to affect a performance parameter of the core of the nuclear reactor. The configurable unit cell further includes a plurality of channels defined within the core block material. Each channel of the plurality of channels is configured to engage an interchangeable component of the plurality of interchangeable components in an operating configuration. Each channel of the plurality of channels is separated from an adjacent channel of the plurality of channels by a predetermined pitch.

Systems and methods are described herein for real-time data processing and for emergency planning. Scenario test data may be collected in real-time based on monitoring local or regional data to ascertain any anomaly phenomenon that may indicate an imminent danger or of concern. A computer-implemented method may include filtering a plurality of different test scenarios to identify a sub-set of test scenarios from the plurality of different test scenarios that may have similar behavior characteristics. A sub-set of test scenarios is provided to a trained neural network to identify one or more sub-set of test scenarios. The one or more identified sub-set of test scenarios may correspond to one or more anomaly test scenarios from the sub-set of test scenarios that is most likely to lead to an undesirable outcome. The neural network may be one of: a conventional neural network and a modular neural network.

The present invention provides a method for integrated online monitoring and a system for integrated online monitoring from a remote location for a nuclear power plant. The method includes a first step of collecting machine monitoring data of a plurality of units in the nuclear power plant selectively from the local data acquisition device via the monitoring data relay device, and a second step of collecting machine diagnostic data of a plurality of units in the nuclear power plant selectively from the local data acquisition device via the diagnostic data relay device.

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 power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

A method for analyzing a sever accident in a nuclear reactor based on an advanced particle method includes steps of: 1) performing geometric modeling, setting initial conditions and boundary conditions; 2) updating material physical properties and key parameters; 3) performing mechanical structure module calculation, updating solid particle stress, strain, internal energy, displacement and velocity; 4) performing thermal hydraulic module calculation, updating fluid particle internal energy, position and velocity; 5) performing chemical reaction module calculation, updating particle matter composition and internal energy; 6) performing neutron physics module calculation, updating particle neutron flux density; and 7) outputting data. The method of the present invention is based on the discrete form of the advanced particle method, which is capable of accurately capturing cross-sectional changes, matter changes, and phase changes. Compared with grid method, the present invention can effectively avoid a mesh distortion problem existing in a large deformation.

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 (100) a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating (110) a reference secondary PCI margin for the reference pattern; calculating (120) a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating (130) 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.