A method regulates operating parameters comprising at least the mean temperature of the core (T.sub.m), and the axial power (AO) imbalance. The method includes development of a vector (U.sub.S) of control values of the nuclear reactor by a supervisor (31) implementing a predictive control algorithm; development of a vector (u.sub.K) of corrective values of the nuclear reactor controls by a regulator (33) implementing a sequenced gain control algorithm; development of a vector (U) of corrected values of the commands of the nuclear reactor, by using the vector (U.sub.S) of the values of the commands produced by the supervisor (31) and the vector (u.sub.K) of the corrective values of the commands produced by the regulator (33); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.

Systems and methods suitable for capable of autonomous crack detection in surfaces by analyzing video of the surface. The systems and methods include the capability to produce a video of the surfaces, the capability to analyze individual frames of the video to obtain surface texture feature data for areas of the surfaces depicted in each of the individual frames, the capability to analyze the surface texture feature data to detect surface texture features in the areas of the surfaces depicted in each of the individual frames, the capability of tracking the motion of the detected surface texture features in the individual frames to produce tracking data, and the capability of using the tracking data to filter non-crack surface texture features from the detected surface texture features in the individual frames.

The present invention discloses a simulation method for three-dimensional full-space plasma response in EAST tokamak. In numerical simulation of plasma response in an EAST tokamak device, firstly, single frequency waves with different frequencies and amplitudes are selected according to experiment needs, to design waveforms of an external perturbation current field; then selected single frequency current field waveforms are respectively used as driving terms to solve magnetohydrodynamic equations containing an external driving current field to solve the distribution of the single frequency magnetic response signals in a three-dimensional full space; and finally, multiple groups of the single frequency magnetic response signals are superimposed and converted into a time domain space to obtain the three-dimensional full-space distribution of plasma magnetic response signals at any time. The present invention realizes the corresponding full-space distribution of plasma at any time in the process of simulating EAST tokamak discharge experiments, and makes up for the deficiency that the distribution of full-space magnetic signals cannot be obtained by experimental measurement. The present invention has accurate simulation results and strong practicality, and is a stable and efficient numerical simulation method.

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.

The present disclosure provides a method of multi-objective and multi-dimensional online joint monitoring for a nuclear turbine. The method includes: obtaining first temperature monitoring data of the nuclear turbine by performing online thermal monitoring on a rotor, a valve cage and a cylinder of the nuclear turbine under quick starting-up; obtaining second temperature monitoring data of tightness of a flange association plane of the cylinder of the nuclear turbine by performing online thermal monitoring on the tightness of the flange association plane; obtaining operation monitoring data of a shafting vibration of a rotor and bearing system of the nuclear turbine by performing online safety monitoring on the shafting vibration of the rotor and bearing system; and optimizing operation and maintenance control of the nuclear turbine according to at least one type of monitoring data among the first temperature monitoring data, the second temperature monitoring data and the operation monitoring data.

Illustrative embodiments provide methods and systems for migrating fuel assemblies in a nuclear fission reactor, methods of operating a nuclear fission traveling wave reactor, methods of controlling a nuclear fission traveling wave reactor, systems for controlling a nuclear fission traveling wave reactor, computer software program products for controlling a nuclear fission traveling wave reactor, and nuclear fission traveling wave reactors with systems for migrating fuel assemblies.

A control rod drive system includes a drive assembly and a cage assembly operably coupled to the drive assembly. The cage assembly includes a plurality of drive rods operably engaged with a drive platform, a plurality of guide rods extending through the drive platform, and a control platform releasably coupled to the drive platform via quick release assembly, the control platform configured to have a control rod mounted thereto. A method of control operation of a nuclear reactor includes receiving instructions to adjust operation of the nuclear reactor, moving a control rod relative to a core of the nuclear reactor via rotating one or more drive rods engaged with a drive platform, and releasing a control platform coupled to the control rod from the drive platform.

A control drum assembly may include a control drum and a control assembly coupled to the control drum through a drive shaft. The control drum assembly may also include a cage assembly. The cage assembly may include one or more structural supports and one or more modular platforms coupled to the one or more structural supports. The one or more modular platforms may be configured to support one or more components of the control assembly. The cage assembly may also include a base configured to be coupled to a surface of a core and to locate the cage assembly relative to the core.

A probabilistic method for determining an operability interval for fasteners in a nuclear power plant assembly is provided. The probabilistic method includes determining or assuming a geometric distribution of a given initial condition of fasteners in the nuclear power plant assembly at an initial time T0; determining a future fastener failure probability model of the geometric distribution over time; generating a plurality of random future fastener failure patterns by applying the fastener failure model to the geometric distribution at a given time T1>T0; postulating fastener spacing rules designed to evaluate the acceptability of fastener failure patterns for the fasteners in the nuclear power plant assembly; applying the fastener spacing rules to a plurality of randomly generated fastener failure patterns for the given time T1 to determine the probability of the randomly generated fastener failure patterns passing the fastener spacing rules at the given time T1; iterating, by a processor of a computer, the applying step for a given range of time values T2, T3, . . . , Tx>T0 and determining a maximum future time Tmax at which a predetermined acceptable probability of the fastener failure patterns passing the fastener spacing rules is met, thereby justifying the acceptability of the fasteners for continued operation of the nuclear power plant assembly; and determining the operability interval as being Tmax-T0.

Illustrative embodiments provide methods and systems for migrating fuel assemblies in a nuclear fission reactor, methods of operating a nuclear fission traveling wave reactor, methods of controlling a nuclear fission traveling wave reactor, systems for controlling a nuclear fission traveling wave reactor, computer software program products for controlling a nuclear fission traveling wave reactor, and nuclear fission traveling wave reactors with systems for migrating fuel assemblies.