Author: Louis Glenn RayesPublisher:
ISBN:
Category :
Languages : en
Pages : 256
Book Description
System Identification of a Nuclear Boiling Water Reactor Model
Author: Louis Glenn RayesSystem Identification, Estimation, and Optimal Feedback Control Theory Applied to the Control of a Nuclear Boiling Water Reactor
Author: Bjørn FrognerBoiling Water Reactor Stability Analysis by Stochastic Transfer Function Identification
Author: Minsun OuyangPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 502
Book Description
Nuclear Reactor Noise Analysis for Surveillance and System Identification Via Dynamic Data System Methodology
Author: Min Chan ChowPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 376
Book Description
Boiling Water Reactors
Author: U.S. Atomic Energy CommissionPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 56
Book Description
Parameter Identification and Malfunction Detection in Nuclear Reactor Systems
Author: Shahla KeyvanIdentification of Unresolved Safety Issues Relating to Nuclear Power Plants
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Program Support BranchPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 108
Book Description
Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code CTF.
Author: Christopher GosdinPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
CTF, the version of the thermal-hydraulic sub-channel code COBRA-TF being jointly developed and maintained by Pennsylvania State University (PSU) and Oak Ridge National Laboratory (ORNL) for applications in the U.S. Department of Energy (DOE) supported Consortium for Advanced Simulation of Light Water Reactors (CASL) project, uses a two-fluid, three-field representation of two-phase flow, which makes the code capable of modeling two-phase flow in Boiling Water Reactors (BWR) during nominal operating conditions. The sub-channel code CTF is used for Pressurized Water Reactors (PWR) for best-estimate evaluations of the nuclear reactor safety margins; however, due to its capabilities, CTF is powerful and valuable computational tool for modeling BWRs. CTF has been subjected to a strict verification procedure, by addressing the mathematical accuracy of the numerical solutions on multiple stages. The code was then validated using numerous of experimental databases, including the U.S. Nuclear Regulatory Commission (NRC) / Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA-OECD) Boiling Water Reactor Full Bundle Tests (BFBT) Benchmark. The BFBT benchmark contains a large amount of test cases representative of BWRs steady-state and off-nominal operating conditions, which makes it one of the most widely used benchmark for validating BWR modeling tools. Two of the main experimental tests involve critical power tests and void distribution tests. Specific experimental cases were chosen and simulated using CTF. Statistical studies were carried out on the void distribution cases to evaluate the code modeling uncertainties. This thesis also focuses on application of CTF to mini- and whole-core BWR calculations on a pin-cell resolved level; as well as on demonstrating that CTF can properly model bypass flow in BWR cores. To increase the confidence in the CTF's BWR modeling capabilities, extensive simulations have been performed using the international NEA-OECD / US NNRC Oskarshamn-2 benchmark, including modeling of a single and 2x2 assemblies on a pin-by-pin level, and a full core model on an assembly level. Each model is varied, with an increasing amount of detail. The results demonstrate that CTF is capable of modeling basic and complex BWR core configurations and operating conditions. Using the three Oskarshamn-2 simulations, CTF's capabilities of modeling BWRs was further verified.
Boiling Water Reactor Off-gas Systems Evaluation
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Environmental Evaluation BranchPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 50
Book Description
Trends and Progress in System Identification
Author: Pieter EykhoffPublisher: Elsevier
ISBN: 1483148661
Category : Mathematics
Languages : en
Pages : 419
Book Description
Trends and Progress in System Identification is a three-part book that focuses on model considerations, identification methods, and experimental conditions involved in system identification. Organized into 10 chapters, this book begins with a discussion of model method in system identification, citing four examples differing on the nature of the models involved, the nature of the fields, and their goals. Subsequent chapters describe the most important aspects of model theory; the ""classical"" methods and time series estimation; application of least squares and related techniques for the estimation of dynamic system parameters; the maximum likelihood and error prediction methods; and the modern development of statistical methods. Non-parametric approaches, identification of nonlinear systems by piecewise approximation, and the minimax identification are then explained. Other chapters explore the Bayesian approach to system identification; choice of input signals; and choice and effect of different feedback configurations in system identification. This book will be useful for control engineers, system scientists, biologists, and members of other disciplines dealing withdynamical relations.