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E-raamat: Linear and Non-linear Stability Analysis in Boiling Water Reactors: The Design of Real-Time Stability Monitors

(Metropolitan Autonomous University Campus Iztapalapa (UAM-I), Mexico), (Professor of Transport Phenomena, Nuclear Engineering and Reactor Physics / Applied Mathematics, Metropolitan Autonomous University Campus Iztapalapa (UAM-I), Mexic)
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Linear and Non-Linear Stability Analysis in Boiling Water Reactors: The Design of Real-Time Stability Monitors presents a thorough analysis of the most innovative BWR reactors and stability phenomena in one accessible resource. The book presents a summary of existing literature on BWRs to give early career engineers and researchers a solid background in the field, as well as the latest research on stability phenomena (propagation phenomena in BWRs), nuclear power monitors, and advanced computer systems used to for the prediction of stability. It also emphasizes the importance of BWR technology and embedded neutron monitoring systems (APRMs and LPRMs), and introduces non-linear stability parameters that can be used for the onset detection of instabilities in BWRs.

Additionally, the book details the scope, advantages, and disadvantages of multiple advanced linear and non linear signal processing methods, and includes analytical case studies of existing plants. This combination makes Linear and Non-Linear Stability Analysis in Boiling Water Reactors a valuable resource for nuclear engineering students focusing on linear and non-linear analysis, as well as for those working and researching in a nuclear power capacity looking to implement stability methods and estimate decay ratios using non-linear techniques.

  • Explores the nuclear stability of Boiling Water Reactors based on linear and non-linear models
  • Evaluates linear signal processing methods such as autoregressive models, Fourier-based methods, and wavelets to calculate decay ratios
  • Proposes novel non-linear signal analysis techniques linked to non-linear stability indicators
  • Includes case studies of various existing nuclear power plants as well as mathematical models and simulations
1 Stability in boiling water reactors: Models and digital signal processing
1(24)
1.1 Nuclear power plants and their impact in our world
1(2)
1.2 BWR and the stability issue
3(5)
1.3 Dynamical analysis in BWR: Introducing codes
8(4)
1.4 Digital signal processing and nuclear reactors
12(6)
1.5 Toward a new paradigm in BWR stability analysis: Models and digital signal processing, a nonlinear approach
18(7)
2 Description of boiling water reactors
25(32)
2.1 Power generation
25(4)
2.2 Boiling water reactor: Development and evolution
29(4)
2.3 Boiling water reactor of generation II
33(5)
2.4 Boiling water reactor of generation III
38(7)
2.5 Boiling water reactor of generation III+
45(8)
2.6 Power uprate in boiling water reactors
53(4)
3 Instability phenomena in BWRs
57(56)
3.1 Types of instabilities
57(1)
3.2 Static instabilities
57(24)
3.3 Dynamic instabilities
81(12)
3.4 In-phase instability
93(3)
3.5 Out-of-phase instability
96(2)
3.6 Partial out-of-phase oscillation
98(3)
3.7 Instability events in operating power plants and lessons learned
101(5)
3.8 Instabilities produced by the control system
106(1)
3.9 Thermal-acoustic oscillations in BWRs
106(7)
4 Propagation phenomena in boiling water reactors
113(80)
4.1 Void wave propagation speed
113(38)
4.2 Pressure wave propagation speed
151(8)
4.3 Heat wave propagation speed
159(25)
4.4 Neutronic wave propagation speed
184(5)
4.5 Magnitude order of wave propagation speed in BWR
189(4)
5 Dynamics of BWRs and mathematical models
193(76)
5.1 Neutron density dynamic model
193(1)
5.2 Approximation P1 of the transport equations
194(5)
5.3 Neutron diffusion coefficients in nuclear reactors
199(15)
5.4 Neutron point kinetics equations
214(4)
5.5 Fuel heat transfer dynamics in nuclear reactor
218(2)
5.6 Feedback mechanism
220(6)
5.7 Reduced order model (ROM)
226(8)
5.8 Linear analysis with effects of neutron relaxation times
234(10)
5.9 Decay ratio as linear stability indicator
244(3)
5.10 Nonlinear analysis
247(22)
6 Linear signal processing methods and decay ratio estimation
269(46)
6.1 Classical spectral estimation: Fourier transform-based methods
269(12)
6.2 Modern spectral estimation: Autoregressive model-based methods
281(8)
6.3 Decay ratio estimation based on the FFT and AR models
289(3)
6.4 Wavelet-based methods and DR estimation
292(16)
6.5 Application of the multiresolution analysis
308(2)
6.6 Application of the continuous wavelet transform
310(1)
6.7 Other linear methods
310(5)
7 Nonlinear signal processing methods: DR estimation and nonlinear stability indicators
315(84)
7.1 Empirical mode decomposition
315(29)
7.2 Hilbert-Huang transform
344(3)
7.3 Estimation of DR and out-of-phase oscillations based on EMD-HHT
347(7)
7.4 Introducing nonlinear stability indicators
354(7)
7.5 Numerical experiments with synthetic signals
361(8)
7.6 Applications in real nuclear power plants
369(28)
7.7 Final remarks: DR, SE, and LLE
397(2)
8 Linear and nonlinear monitor for BWR: Implementation and performance
399(34)
8.1 Benchmarks data: Forsmark and Ringhals
399(3)
8.2 Monitoring system in a BWR
402(5)
8.3 Stability monitor implementation: Algorithms and performance
407(19)
8.4 The real-time implementation issue
426(7)
Abbreviations 433(4)
References 437(18)
Index 455
Dr. Alfonso Prieto-Guerrero received his PhD in Sciences in Digital Signal Processing from the National Polytechnics Institute of Toulouse, France. He is currently working at the Metropolitan Autonomous University Campus Iztapalapa (UAM-I), Mexico and his research interests focus on the domain of signal processing and its applications. Dr. Prieto-Guerrero has worked on signal compression, speaker recognition,and communications applications, and is currently collaborating on projects related to nuclear reactor signals. In 2007, he spent time at the TESA laboratory (Telecommunications for space and aeronautics) in Toulouse, France, where he collaborated in the regional project OURSES on biomedical applications via satellite. In 2014, he was awarded the Best Paper Award at the Thermal-Hydraulics international conference (NUTHOS-10). Dr. Gilberto Espinosa-Paredes is Professor of Transport Phenomena, Nuclear Engineering and Reactor Physics, and Applied Mathematics at the Metropolitan Autonomous University Campus Iztapalapa (UAM-I), where he has been since 1997. Dr. Espinosa-Paredes recently served as Guest Editor of Science and Technology of Nuclear Installations on Severe Accident Analysis in Nuclear Power Plants, and has served on numerous editorial boards. Dr. Espinosa-Paredes is a member of the Mexican Engineering Academy, Science Mexican Academy, and Level III of the Mexican National System of Researchers (SNI). He has around 200 publications on nuclear energy and geoenergy; in 2014, he was awarded the Best Paper Award at the Thermal-Hydraulics international conference (NUTHOS-10). Dr. Espinosa-Paredes is well regarded as an expert in mathematical modeling applied to analysis and nuclear safety.