Nuclear Reactor Control Assembly for Flexible Power Transients
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Solution Overview
Problem
Nuclear reactors operating in base load mode face challenges in power variations due to their design, leading to inefficiencies and increased costs when transitioning between power outputs, especially during market price fluctuations, and existing solutions for flexibility are costly and time-consuming.
Innovation Solution
A method and control assembly for nuclear reactors that iteratively generate an injection sequence of neutron poison and water into the primary coolant using a predictive model, optimizing power variations by calculating core state evolution and minimizing a cost function, allowing for rapid and flexible power transients without significant system modifications.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Stability of the object's composition
If nuclear reactors operate in base load mode (mode A), then reactor stability is maintained, but power variation flexibility is reduced
Solution Approach 1:
The patent implements a dynamic control system that adapts the reactor's operating mode between base load (mode A) and load following (mode G) based on real-time market conditions and operational requirements. The supervisor controller dynamically adjusts control parameters and injection sequences to enable flexible power variations while maintaining stability through predictive modeling and iterative optimization.
2Adaptability or versatility
If control mode is changed from mode A to mode G, X, T or ALFC, then power flexibility is improved, but system complexity and cost increase
Solution Approach 1:
The patent creates a universal control assembly that can operate in multiple modes (A and G) using the same hardware infrastructure. The supervisor controller and predictive model enable the system to switch between base load and load following modes without requiring separate dedicated systems, thereby reducing overall complexity while maintaining flexibility.
Solution Approach 2:
The patent uses a predictive model that creates a virtual copy of the reactor core to simulate and optimize control sequences before actual implementation. This digital twin approach allows for testing and optimization without physical modifications, reducing the complexity of the physical control system while enabling sophisticated power variation capabilities.
3Measurement precision
If online CMS simulation tools are used, then power transient accuracy is improved, but calculation speed decreases
Solution Approach 1:
The patent performs preliminary calculations and optimizations offline to generate predictive models and pre-computed control sequences. The supervisor controller then uses these pre-prepared models for rapid real-time decision-making, combining the accuracy of detailed simulations with the speed needed for operational responsiveness.
Solution Approach 2:
The patent applies a simplified predictive model for real-time control that captures the essential physics without the full complexity of online CMS simulations. This partial modeling approach provides sufficient accuracy for operational control while achieving the calculation speed required for real-time applications.
4Adaptability or versatility
If RMOSC operating method is implemented, then power flexibility is improved, but instrumentation modification cost increases
Solution Approach 1:
The patent merges the supervisor controller with the existing control assembly, integrating multiple functions (predictive modeling, optimization, and control) into a single unified system. This consolidation reduces the need for separate instrumentation modifications and leverages existing hardware resources, thereby lowering implementation costs while maintaining power flexibility.
Data Source
AI summary
A method for controlling a nuclear reactor includes acquiring current values of operating parameters of the reactor; and iteratively implementing the sub-steps of generating a sequence of injection of neutron poison and/or water; calculating an evolution in at least one magnitude characteristic of the state of the core of the nuclear reactor during this given time interval using a power program, current values of operating parameters and the injection sequence considered, the evolution being calculated using a predictive model of the core of the reactor; evaluating a cost function, using the calculated evolution; repeating the generating and calculating sub-steps until a convergence criterion of the cost function is met; and repeating the acquiring and the iteratively implementing steps with a time period less than 60 minutes.


