Fault tolerant control for increased safety and security of nuclear power plants

Lead Research Organisation: University of Portsmouth
Department Name: Sch of Energy and Electronic Engineering

Abstract

In safety-critical systems, such as nuclear power plants, the demand for reliability, safety and fault tolerance is high. Faults compromise plant safety, cause inefficiencies in the operation of industrial processes and reduce component life. In such safety-critical systems, it is useful to design control systems which are capable of tolerating potential faults to improve the reliability and availability while providing a desirable performance. A control system which can automatically tolerate component malfunctions, while maintaining desirable performance and stability properties is said to be a fault-tolerant control system

Fault tolerant control approaches allow control systems to operate under fault conditions with minimal degradation of performance and stability, preventing localised, random, or intentional faults from developing into catastrophic system failures leading to accidents that may have severe consequences to human life, equipment, infrastructure, or the environment. Fault tolerance helps to reduce the damaging effects that faults can have while remedial action is taken to repair or eliminate the fault.

The proposed work will develop a hierarchical fault-tolerant control scheme for PWR nuclear power plants which will be defined over three levels: execution, coordination and management levels. The execution level, which includes the reactor, steam generator and turbine, implements the control actions generated by the higher levels through actuators, senses relevant plant variables, and passes this information to the higher levels. The middle level acts as a coordinator between the plant manager level and the execution level. To maximise its capabilities, the coordination level will include a bank of four different controllers that will be designed to tolerate faults of different severity, and there will be a mechanism to select the most appropriate controller given the circumstances of the plant as required by the management level. The coordination level also contains a diagnostic and prognostic system, which will the plant data and knowledge about the useful life of components to detect and characterise sensor related and other plant faults. The top level manages plant performance monitoring, plant condition evaluation, and passes commands to the coordination level. In addition, the management level transmits operational data to and receives instructions from a central command, control, and communication system which interfaces with human operators.

The project will also involve the development of a nuclear plant simulator which will be used to test in real-time the hierarchical fault tolerant control scheme to be developed and implemented, to generate data about the behaviour of the plant under normal and fault conditions, and to generate simplified models of the plant, or parts of the plant, to be used for the purposes of controller design. The real-time tests will permit to assess the developments in a computational environment that is close to what would be encountered on a real plant, hence ensuring that the control methods to be developed are as realistic as possible.

The work will be carried out in collaboration with Bhabha Atomic Research Centre, an Indian research institution that specialises in nuclear energy, and will benefit from the involvement of STS Nuclear, a UK organisation that specialises in nuclear safety management and training.

Planned Impact

The outcomes of the project will be very relevant to the nuclear energy industry in the UK, India and beyond. The project aims to develop and test a hierarchical integrated fault-tolerant control architecture for PWR nuclear power plants. The methods, software, underlying models, and data that will form the end-result of this project will be a suitable starting point for additional work aiming to increase the readiness level of the technology and ultimately incorporate it on a real plant.

Some of the methods and models to be developed could also be of use to the atomic energy and environmental authorities as benchmarks of achievable control system performance following component faults in a nuclear power plant, so that they can compare with the performance of existing control approaches and decide how the adoption of the fault-tolerant control approaches to be developed in this project may benefit plant safety, reliability and availability

In addition, we expect the fault tolerant control, automatic sensor calibration, and fault detection and diagnosis techniques to be developed as part of this project to be of interest in other safety-critical areas outside the nuclear industry, including for example aircraft control systems, autonomous vehicles, and chemical processes. These control methods for processes subject to faults are expected to significantly improve the operation and performance of plants, increase plant safety and reliability, and minimize the negative economic impact of failures on overall plant operation. This research addresses the design of feedback control and estimation systems accounting explicitly for the occurrence of faults and uniquely integrates controller design, fault-detection and isolation, sensor calibration and validation, and decision support technologies, and it provides the potential for significant insight on the trade-offs that can exist between these in practical implementation.

The development of software, the organisation of an end-of-project workshop, and the collaboration with our partners IGCAR and STS Nuclear will be the principal means for transferring the results of this research into the industrial sector, and of seeking ways to achieve the transfer of project results.
 
Description The following key findings have been achieved so far in this project. These are building blocks that will contribute to the achievement of the objectives of this project.

1) A control-oriented model of a pressurised-water type nuclear plant and its low-level control loops has been developed.
2) Robust-optimal integrated control design techniques for a pressurized water-type nuclear power plant have been proposed.
3) The application of a robust controller to control the power loop of a pressurised heavy water (PWR) nuclear reactor has been studied.
5) An approach for model predictive control of pressurised-water type nuclear reactor using multi-scale subspace identification has been investigated.
6) An approach based on linear-matrix-inequalities for robust controller design of pressurised water-type reactors with uncertainty has been studied.
7) A methodology has been proposed for designing a subspace-based gain scheduled predictive controller for nuclear reactor power control.
8) An interval approach for stability analysis of a pressurized water-type reactor with parametric uncertainty has been investigated.
9) A robust subspace predictive control methodology based on integral sliding mode for a pressurized water reactor has been proposed.
10) A disturbance observer-based subspace predictive control of a pressurized water type nuclear reactor has been developed.
11) Transient interactions between a PWR nuclear power plant and a faulted electricity grid have been analysed.
12) An approach for L1-adaptive robust control design for a pressurized water-type nuclear power plant has been proposed and tested through simulations.
13) An LQGI/LTR based robust control technique for a pressurized water nuclear power plant has been created and tested by means of simulations.
14) A method for nonlinear model predictive control using feedback linearization for a pressurized water nuclear power plant has been developed and tested by means of simulations.

These works have been published in the journals "Progress in Nuclear Energy", "Nuclear Engineering and Design", "Annals of Nuclear Energy", "Energies", "IEEE Access", "IEEE Transactions on Nuclear Science" or have been presented in international conferences: The 7th International Conference on Control, Mechatronics and Automation (ICCMA), 15th European Workshop on Advanced Control and Diagnosis, ACD 2019, 2020 28th Mediterranean Conference on Control and Automation (MED), 13th International Conference on Developments in eSystems Engineering, (DeSE 2020), 7th International Conference on Control, Decision and Information Technologies (CoDIT'2020), 8th International Conference on Control, Mechatronics and Automation, (ICCMA 2020).
Exploitation Route The work may be adopted by researchers and engineers who develop control approaches for nuclear reactors. We have either made our collaborators at the Indira Gandhi Centre for Atomic Research and the Bhabha Atomic Research Centre aware of the work, or we have worked with them in developing the approaches that have been proposed so far.
Sectors Energy

URL https://www.port.ac.uk/research/research-projects/fault-tolerant-control-for-increased-safety-and-security-of-nuclear-power-plants
 
Description Our work on L1-adaptive control of nuclear power plants emerging from this project has been used by Jiuwu Hui from the State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, Shenzhen, 518172, Guangdong, China, for the design of an adaptive fault-tolerant control scheme for load following of a modular high-temperature gas-cooled reactor, as evidenced in this publication: https://www.sciencedirect.com/science/article/pii/S0360544222015663 The same work has also been used by the Science and Technology on Altitude Simulation Laboratory, AECC Sichuan Gas Turbine Establishment, Mianyang, 621703, China, for the design of an L1 adaptive control scheme for an aero propulsion system test facility, as evidenced by this publication: https://www.sciencedirect.com/science/article/pii/S1270963823003541 The same work has been used by the Bhabha Atomic Research Centre, India, for the design of an adaptive control scheme for a nuclear reactor, as evidenced by this publication: https://www.sciencedirect.com/science/article/pii/S0029549323001255
First Year Of Impact 2022
Sector Energy
Impact Types Policy & public services

 
Description Influence of our work on L1-adaptive control of nuclear power plants.
Geographic Reach Asia 
Policy Influence Type Influenced training of practitioners or researchers
 
Title Model of a pressurised water-type nuclear power plant 
Description We published complete details of a dynamic model for the simulation and control design of a pressurized water-type nuclear power plant. Although the model cannot be published in software form due to export restrictions, it was fully described in the following publication: Vajpayee, V., Becerra, V., Bausch, N., Deng, J. M., Shimjith, S. R., & Arul, A. J. (2020). Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant. Nuclear Engineering and Design, 370, [110901]. https://doi.org/10.1016/j.nucengdes.2020.110901 
Type Of Material Computer model/algorithm 
Year Produced 2020 
Provided To Others? No  
Impact This publication has been cited 42 times as of 6 March 2024, according to Google Scholar. 
URL https://www.sciencedirect.com/science/article/pii/S0029549320303952?via%3Dihub
 
Title Various actuator and sensor faults for nuclear power plants 
Description The datasets include the bias and drift faults in sensors, and offset and saturation faults in actuators in five different loops of a PWR plant. In total, there are 20 faults. A description of the faults is provided below: F1 Offset in pressurizer level actuator . F2 Saturation in pressurizer level actuator. F3 Bias in pressurizer level sensor. F4 Drift in pressurizer level sensor. F5 Offset added to the turbine-governor valve (steam pressureloop) signal. F6 Saturation on turbine-governor valve (steam pressure loop) . F7 Bias on steam generator sensor . F8 Drift on steam generator sensor. F9 Offset on pressurizer heater F10 Saturation on pressurizer heater. F11 Bias on pressurizer pressure sensor. F12 Drift on pressurizer pressure sensor. F13 Offset turbine governor-valve (turbine speed control). F14 Saturation on turbine-governor valve (turbine speed control) . F15 Bias on turbine speed sensor. F16 Drift on turbine speed sensor. F17 Offset on control rod actuator. F18 Saturation on control rod actuator. F19 Bias on power sensor. F20 Drift on power sensor 
Type Of Material Database/Collection of data 
Year Produced 2022 
Provided To Others? No  
Impact This is just developed in Late 2022. 
URL https://ieeexplore.ieee.org/abstract/document/9967986
 
Title Various faults of sensors and actuators in a reactor core 
Description . A. TYPES OF FAULTS Six single faults and two simultaneous faults are generated. The types of faults considered included bias, drift, actuator offset, and actuator, saturation faults, which are described as follows: Bias fault. This is one of the most common faults in sensors, corresponding to a constant offset added to the sensor output, which may be caused by inappropriate calibration or physical changes in the sensor . Bias failures are common faults in reactor cores, and their maintenance can be costly . The bias fault is injected into the power and temperature sensors at a certain time. Drift fault. This consists of a time-varying offset. The drift fault is difficult to detect because the drifting amplitudes initially low , therefore it is important to have a sensor drift fault. Drift faults are common and can cause power reduction. As with the bias fault, the drift fault is injected into the power and temperature sensors at a certain time. Actuator saturation fault. This is when the actuator (control rod system) exceeds a set saturation value. This phenomenon inevitably must be considered because of physical limitations that, in practice, can led to important deterioration of the system. Actuator offset fault. This corresponds to an offset added to the control rod system at a certain time. This failure can occur because of design/ manufacturing defects in the actuator. These are eight faults in this datasets: Fault ID Process variable Type Fault 1 Reactivity Actuator offset fault Fault 2 Reactivity Actuator saturation fault Fault 3 Power Power sensor bias fault ( Fault 4 Power Power sensor drift fault Fault 5 Temperature Temperature sensor bias fault Fault 6 Temperature Temperature sensor drift fault Fault 7 Reactivity/ Power Actuator saturation fault + Power sensor bias fault Fault 8 Reactivity/ Power Actuator saturation fault + Power sensor drift fault 
Type Of Material Database/Collection of data 
Year Produced 2022 
Provided To Others? Yes  
Impact The paper has been cited in three papers. 
URL https://ieeexplore.ieee.org/stamp/stamp.jsp?arnumber=9706445
 
Description Fault tolerant control for increased safety and security of nuclear power plants 
Organisation Bhabbha Atomic Research Centre
Country India 
Sector Public 
PI Contribution This is an ongoing EPSRC project funded by Phase 4 UK-India Civil Nuclear Energy Programme. There are two postdocs, one at the University of Portsmouth and one at Leeds Becket University. There is collaboration with BARC and IGCAR, both of which are Indian nuclear research laboratories.
Collaborator Contribution The Portsmouth and Leeds Beckett teams carry out most of the research with input from the Indian partners. Interaction and exchange of ideas is achieved through regular teleconferences and visits.
Impact The collaboration is multi-disciplinary, mainly involving the subjects of control engineering and nuclear engineering. Nineteen outputs have been produced out of this research, including eight journal publications which have appeared in top journals including IEEE Transactions in Nuclear Technology, IEEE Access, Nuclear Engineering Progress, etc, and 11 conference publications. These outputs are listed in the output section of this project in ResearchFish. Professor Becerra gave a seminar in BARC on 7 January 2020 entitled "Computational optimal control and estimation using direct collocation methods".
Start Year 2018
 
Description Fault tolerant control for increased safety and security of nuclear power plants 
Organisation Indira Gandhi Centre for Atomic Research (IGCAR)
Country India 
Sector Academic/University 
PI Contribution This is an ongoing EPSRC project funded by Phase 4 UK-India Civil Nuclear Energy Programme. There are two postdocs, one at the University of Portsmouth and one at Leeds Becket University. There is collaboration with BARC and IGCAR, both of which are Indian nuclear research laboratories.
Collaborator Contribution The Portsmouth and Leeds Beckett teams carry out most of the research with input from the Indian partners. Interaction and exchange of ideas is achieved through regular teleconferences and visits.
Impact The collaboration is multi-disciplinary, mainly involving the subjects of control engineering and nuclear engineering. Nineteen outputs have been produced out of this research, including eight journal publications which have appeared in top journals including IEEE Transactions in Nuclear Technology, IEEE Access, Nuclear Engineering Progress, etc, and 11 conference publications. These outputs are listed in the output section of this project in ResearchFish. Professor Becerra gave a seminar in BARC on 7 January 2020 entitled "Computational optimal control and estimation using direct collocation methods".
Start Year 2018
 
Description Fault tolerant control for increased safety and security of nuclear power plants 
Organisation Leeds Beckett University
Country United Kingdom 
Sector Academic/University 
PI Contribution This is an ongoing EPSRC project funded by Phase 4 UK-India Civil Nuclear Energy Programme. There are two postdocs, one at the University of Portsmouth and one at Leeds Becket University. There is collaboration with BARC and IGCAR, both of which are Indian nuclear research laboratories.
Collaborator Contribution The Portsmouth and Leeds Beckett teams carry out most of the research with input from the Indian partners. Interaction and exchange of ideas is achieved through regular teleconferences and visits.
Impact The collaboration is multi-disciplinary, mainly involving the subjects of control engineering and nuclear engineering. Nineteen outputs have been produced out of this research, including eight journal publications which have appeared in top journals including IEEE Transactions in Nuclear Technology, IEEE Access, Nuclear Engineering Progress, etc, and 11 conference publications. These outputs are listed in the output section of this project in ResearchFish. Professor Becerra gave a seminar in BARC on 7 January 2020 entitled "Computational optimal control and estimation using direct collocation methods".
Start Year 2018
 
Description Impact workshop 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact This online workshop presented the work carried out under the EPSRC UK-India Civil Nuclear Energy Programme Phase 4 funded project "Fault-Tolerant Control For Increased Safety And Security of Nuclear Power Plants" (grants EP/R022062/1 and EP/R021961/1). The work at the University of Portsmouth and Leeds-Beckett University, UK, in collaboration with the Bhabha Atomic Research Centre, Mumbai, India, and Indira Gandhi Centre for Atomic Research, Kalpakkam, India. The workshop presented the various findings and achievements of the project during this period. It included six talks of between 20 to 30 minutes each, a Q & A session, and a panel discussion. It had a total duration of 4 hours and an attendance of 24 individuals from the UK and India, including academics, researchers, postgraduate students, and project collaborators. The workshop took place on 14 December 2021.
Year(s) Of Engagement Activity 2021
URL https://www.eventbrite.co.uk/e/workshop-on-the-fault-tolerant-control-of-nuclear-power-plants-ticket...
 
Description Seminar 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach Local
Primary Audience Industry/Business
Results and Impact Professor Becerra gave a seminar at the Bhaba Atomic Research Centre (BARC) on 7 January 2020 entitled "Computational optimal control and estimation using direct collocation methods".
Year(s) Of Engagement Activity 2020
 
Description Seminar by Professor Victor Becerra in Workshop on Nuclear Energy and Measurement 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Other audiences
Results and Impact This was an online workshop on Nuclear Energy and Measurement organised by the Department of Instrumentation and Control Engineering at the National Institute of Technology Tiruchirappalli, Tamil Nadu, India.

The workshop was sponsored by the SPARC programme. The Scheme for Promotion of Academic and Research Collaboration (SPARC) aims at improving the research
ecosystem of India's higher educational institutions by facilitating academic and research collaborations between Indian institutions and the best institutions in the world from 28 selected nations to jointly solve problems of national and international relevance.

The workshop took place between 23rd and 25th September 2021.

Professor Becerra's talk was entitled: "Adaptive Robust Control Design for a Pressurized Water-Type Nuclear Power Plant", it was delivered on 23 September 2021 and lasted for 1 hour. He was the only foreign speaker in the workshop.

The audience included academics, postgraduate students, engineers, and scientists from industry and national laboratories. Over 50 people attended the workshop.
Year(s) Of Engagement Activity 2021
URL https://www.nitt.edu/home/SPARC_ICE.pdf