Nonlinear Dynamic Modeling and Simulation of a Passively Cooled Small Modular Reactor

Nonlinear Dynamic Modeling and Simulation of a Passively Cooled Small Modular Reactor

Author: Samet Egemen Arda

Publisher:

Published: 2016

Total Pages: 142

ISBN-13:

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A nonlinear dynamic model for a passively cooled small modular reactor (SMR) is developed. The nuclear steam supply system (NSSS) model includes representations for reactor core, steam generator, pressurizer, hot leg riser and downcomer. The reactor core is modeled with the combination of: (1) neutronics, using point kinetics equations for reactor power and a single combined neutron group, and (2) thermal-hydraulics, describing the heat transfer from fuel to coolant by an overall heat transfer resistance and single-phase natural circulation. For the helical-coil once-through steam generator, a single tube depiction with time-varying boundaries and three regions, i.e., subcooled, boiling, and superheated, is adopted. The pressurizer model is developed based upon the conservation of fluid mass, volume, and energy. Hot leg riser and downcomer are treated as first-order lags. The NSSS model is incorporated with a turbine model which permits observing the power with given steam flow, pressure, and enthalpy as input. The overall nonlinear system is implemented in the Simulink dynamic environment. Simulations for typical perturbations, e.g., control rod withdrawal and increase in steam demand, are run. A detailed analysis of the results show that the steady-state values for full power are in good agreement with design data and the model is capable of predicting the dynamics of the SMR. Finally, steady-state control programs for reactor power and pressurizer pressure are also implemented and their effect on the important system variables are discussed.


Dynamic Modeling of a Small Modular Reactor for Control and Monitoring

Dynamic Modeling of a Small Modular Reactor for Control and Monitoring

Author: Jeffrey Robert Kapernick

Publisher:

Published: 2015

Total Pages: 154

ISBN-13:

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A system model of the Babcock & Wilcox Generation mPower small modular reactor (SMR) was developed within the MATLAB-Simulink environment. A detailed physical configuration of this SMR was established based on the limited information available for the mPower reactor. This is an important step in the development of the simulation model. Three mathematical models were combined to simulate the control dynamics. A lumped-parameter approximation of fuel-to-coolant heat transfer is combined with vessel upper plenum and lower plenum coolant masses to represent the core power and heat transfer dynamics. A nodalized moving boundary steam generator model balances mass, momentum, and energy for the sub-cooled, saturated, and superheated flow regimes. A component based balance-of-plant system calculates the feedwater temperature. Controllers for the system include a once-through steam generator program which maintains a constant average primary coolant temperature with reactor thermal power, and a constant steam pressure controller, which maintains the steam outlet pressure at the set point by throttling the main steam valve. The integrated plant model is used to generate normal operation data and simulation of plant operation under specified transients. These data are being used for developing and testing on-line monitoring techniques for small modular reactors.


Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor

Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor

Author: Ravindra Munje

Publisher: Springer

Published: 2017-10-13

Total Pages: 184

ISBN-13: 9811030146

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This book examines the different spatial control techniques for regulation of spatial power distribution in advanced heavy water reactors (AHWR). It begins with a review of the literature pertinent to the modeling and control of large reactors. It also offers a nodal-core model based on finite difference approximation since the AHWR core is considered to be divided into 17 relatively large nodes. Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR. The book also presents a vectorized nonlinear model of AHWR and implements it in MATLAB/Simulink environment. The model of the reactor is then linearized at the rated power and put into standard state variable form. It is characterized by 90 states, 5 inputs and 18 outputs. Lastly, it discusses control techniques for a nonlinear model of AHWR. This book will prove to be a valuable resource for professional engineers and implementation specialists, researchers and students.


Update on Small Modular Reactors Dynamics System Modeling Tool -- Molten Salt Cooled Architecture

Update on Small Modular Reactors Dynamics System Modeling Tool -- Molten Salt Cooled Architecture

Author:

Publisher:

Published: 2014

Total Pages: 111

ISBN-13:

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The Small Modular Reactor (SMR) Dynamic System Modeling Tool project is in the third year of development. The project is designed to support collaborative modeling and study of various advanced SMR (non-light water cooled) concepts, including the use of multiple coupled reactors at a single site. The objective of the project is to provide a common simulation environment and baseline modeling resources to facilitate rapid development of dynamic advanced reactor SMR models, ensure consistency among research products within the Instrumentation, Controls, and Human-Machine Interface (ICHMI) technical area, and leverage cross-cutting capabilities while minimizing duplication of effort. The combined simulation environment and suite of models are identified as the Modular Dynamic SIMulation (MoDSIM) tool. The critical elements of this effort include (1) defining a standardized, common simulation environment that can be applied throughout the program, (2) developing a library of baseline component modules that can be assembled into full plant models using existing geometry and thermal-hydraulic data, (3) defining modeling conventions for interconnecting component models, and (4) establishing user interfaces and support tools to facilitate simulation development (i.e., configuration and parameterization), execution, and results display and capture.


Scaling, Experiments, and Simulations of Condensation Heat Transfer for Advanced Nuclear Reactors Safety

Scaling, Experiments, and Simulations of Condensation Heat Transfer for Advanced Nuclear Reactors Safety

Author: Palash Kumar Bhowmik

Publisher:

Published: 2021

Total Pages: 199

ISBN-13:

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"The purpose of this research was to perform scaled experiments and simulations to validate computational fluid dynamics (CFD) and empirical models of condensation heat transfer (CHT) for the passive containment cooling system (PCCS) of Small Modular Reactors (SMRs). SMRs are the futuristic candidates for clean, economic, and safe energy generation; however, reactor licensing requires safety system evaluations, such as PCCS. The knowledge in the reviewed relevant literature showed a gap in experimental data for scaling SMR's safety systems and validating computational models. The previously available test data were inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. This study developed three scaled (different diameters) test sections with annular cooling for scale testing and analysis to fill this research gap. First, tests were performed for pure steam and steam with non-condensable gases (NCGs), like nitrogen and helium, at different mass fractions, inlet mass flow rates, and pressure ranges. Second, detailed CFD simulations and validations were performed using STAR-CCM+ software with scaled geometries and experimental parameters (e.g., flow rate, pressure, and steam-NCG mixtures), thus mimicking reactor accident cases. The multi-component gases, multiphase mixtures, and fluid film condensation models were applied, verified, and optimized in the CFD simulations with associated turbulence models. Third, the physics-based and data-driven condensation models and empirical correlations were assessed to quantify the scaling distortions. Finally, the experiments, simulations, and modeling results were evaluated for critical insights into the physics conditions, scaling effects, and multi-component gas mixture parameters. This study supported improvements to nuclear reactor safety systems' modeling capabilities irrespective of size (small or big), and findings were equally applicable to other non-nuclear energy applications"--Abstract, page iii.


Dynamic Simulation of Sodium Cooled Fast Reactors

Dynamic Simulation of Sodium Cooled Fast Reactors

Author: G Vaidyanathan

Publisher: CRC Press

Published: 2022-11-18

Total Pages: 289

ISBN-13: 1000779564

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This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.


Modeling and Performance of the MHTGR (Modular High-Temperature Gas-Cooled Reactor) Reactor Cavity Cooling System

Modeling and Performance of the MHTGR (Modular High-Temperature Gas-Cooled Reactor) Reactor Cavity Cooling System

Author:

Publisher:

Published: 1990

Total Pages: 27

ISBN-13:

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The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S. Department of Energy is designed to remove the nuclear afterheat passively in the event that neither the heat transport system nor the shutdown cooling circulator subsystem is available. A computer dynamic simulation for the physical and mathematical modeling of and RCCS is described here. Two conclusions can be made form computations performed under the assumption of a uniform reactor vessel temperature. First, the heat transferred across the annulus from the reactor vessel and then to ambient conditions is very dependent on the surface emissivities of the reactor vessel and RCCS panels. These emissivities should be periodically checked to ensure the safety function of the RCCS. Second, the heat transfer from the reactor vessel is reduced by a maximum of 10% by the presence of steam at 1 atm in the reactor cavity annulus for an assumed constant in the transmission of radiant energy across the annulus can be expected to result in an increase in the reactor vessel temperature for the MHTGR. Further investigation of participating radiation media, including small particles, in the reactor cavity annulus is warranted. 26 refs., 7 figs., 1 tab.


Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors

Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 423

ISBN-13: 9789201274106

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Based on an IAEA coordinated research project focused on the use of passive safety systems and natural circulation to help meet the safety and economic goals of advanced nuclear power plants, this publication includes the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems, characterization of each phenomenon, integral tests to examine the passive systems and natural circulation, and a methodology for examining passive system reliability.