Modeling And Simulation Of A Prototypical Advanced Reactor
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Modeling And Simulation Of A Prototypical Advanced Reactor
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Author : Xiaotong Liu
language : en
Publisher:
Release Date : 2015
Modeling And Simulation Of A Prototypical Advanced Reactor written by Xiaotong Liu and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015 with categories.
Current online risk monitors provide a point-in-time estimate of the system risk given the current plant configuration (e.g., equipment availability, operational regime, environmental conditions). However, these risk monitors do not account for plant-specific normal, abnormal, and deteriorating states of active components and systems. The lack of operating experience with proposed advanced reactor designs limits our ability to estimate the probability of failure (POF) of key components. Incorporation of unit-specific estimates of POF into dynamic probabilistic risk assessment (PRA) has the potential to enable real-time decisions about stress relief and to support effective maintenance planning while ensuring investment protection. The enhanced risk monitor (ERM) supports the safe and economic operation goals of advanced reactor by providing a dynamic assessment of system risk with real-time estimates of POF and event probability based on equipment condition assessment. A simulation framework for a prototypical advanced reactor (PAR) was developed in this work to provide a platform to demonstrate the ERM. A Simulink model of the PAR was developed, including the primary system, intermediate heat transport loop, steam generator, and balance of plant (BOP). To ensure accuracy across a large range of operating conditions, a nonlinear model for the primary system, including reactor kinetics and heat transfer, was used. A perturbation model of the steam generator showed good performance across the range of conditions and was thus employed. The PAR power block features two independent primary systems, each with dedicated intermediate heat exchangers and steam generators. These two modules are connected to a common BOP through a steam header. To balance the power output of each unit to meet overall power demand, fuzzy control is implemented in the primary system. Degradation of the primary and intermediate sodium pumps is numerically simulated to investigate the effect on overall plant performance. The results indicate that the core power decreases as pump degradation leads to reduced flow in either primary or intermediate loops. The developed PAR model provides simulated power block performance data under component degradation, which can be used to develop and demonstrate the ERM framework.
Advanced Modeling And Simulation Of Nuclear Reactors
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Author : Jingang Liang
language : en
Publisher: Frontiers Media SA
Release Date : 2023-04-10
Advanced Modeling And Simulation Of Nuclear Reactors written by Jingang Liang and has been published by Frontiers Media SA this book supported file pdf, txt, epub, kindle and other format this book has been release on 2023-04-10 with Technology & Engineering categories.
Advanced Reactor Modeling With Matlab
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Author : Riccardo Tesser
language : en
Publisher: Walter de Gruyter GmbH & Co KG
Release Date : 2020-12-07
Advanced Reactor Modeling With Matlab written by Riccardo Tesser and has been published by Walter de Gruyter GmbH & Co KG this book supported file pdf, txt, epub, kindle and other format this book has been release on 2020-12-07 with Technology & Engineering categories.
Offers the reader a modern approach to reactor description and modelling. Using the widely applied numerical language MATLAB, it provides the reader with categorized groups of general code for a wide variety of chemical reactors. Being designed as a tool for researchers and professionals, the code can easily be extended and adapted by the reader to their own specific problems.
Advanced Computational Materials Science
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Author : RE. Stoller
language : en
Publisher:
Release Date : 2004
Advanced Computational Materials Science written by RE. Stoller and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2004 with categories.
The ''Workshop on Advanced Computational Materials Science: Application to Fusion and Generation IV Fission Reactors'' was convened to determine the degree to which an increased effort in modeling and simulation could help bridge the gap between the data that is needed to support the implementation of these advanced nuclear technologies and the data that can be obtained in available experimental facilities. The need to develop materials capable of performing in the severe operating environments expected in fusion and fission (Generation IV) reactors represents a significant challenge in materials science. There is a range of potential Gen-IV fission reactor design concepts and each concept has its own unique demands. Improved economic performance is a major goal of the Gen-IV designs. As a result, most designs call for significantly higher operating temperatures than the current generation of LWRs to obtain higher thermal efficiency. In many cases, the desired operating temperatures rule out the use of the structural alloys employed today. The very high operating temperature (up to 1000 C) associated with the NGNP is a prime example of an attractive new system that will require the development of new structural materials. Fusion power plants represent an even greater challenge to structural materials development and application. The operating temperatures, neutron exposure levels and thermo-mechanical stresses are comparable to or greater than those for proposed Gen-IV fission reactors. In addition, the transmutation products created in the structural materials by the high energy neutrons produced in the DT plasma can profoundly influence the microstructural evolution and mechanical behavior of these materials. Although the workshop addressed issues relevant to both Gen-IV and fusion reactor materials, much of the discussion focused on fusion; the same focus is reflected in this report. Most of the physical models and computational methods presented during the workshop apply equally to both types of nuclear energy systems. The primary factor that differentiates the materials development path for the two systems is that nearly prototypical irradiation environments for Gen-IV materials can be found or built in existing fission reactors. This is not the case for fusion. The only fusion-relevant, 14 MeV neutron sources ever built (such as the rotating target neutron sources, RTNS-I and -II at LLNL) were relatively low-power accelerator based systems. The RTNS-II ''high'' flux irradiation volume was quite small, less than 1 cm{sup 3}, and only low doses could be achieved. The maximum dose data obtained was much less than 0.1 dpa. Thus, RTNS-II, which last operated in 1986, provided only a limited opportunity for fundamental investigations of the effects of 14 MeV neutrons characteristic of DT fusion.
Dynamic Simulation Of Sodium Cooled Fast Reactors
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Author : G Vaidyanathan
language : en
Publisher: CRC Press
Release Date : 2022-11-18
Dynamic Simulation Of Sodium Cooled Fast Reactors written by G Vaidyanathan and has been published by CRC Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2022-11-18 with Technology & Engineering categories.
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.
Foundational Development Of An Advanced Nuclear Reactor Integrated Safety Code
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Author :
language : en
Publisher:
Release Date : 2010
Foundational Development Of An Advanced Nuclear Reactor Integrated Safety Code written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with categories.
This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.
Proceedings Of The 10th World Congress On Engineering Asset Management Wceam 2015
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Author : Kari T. Koskinen
language : en
Publisher: Springer
Release Date : 2016-03-25
Proceedings Of The 10th World Congress On Engineering Asset Management Wceam 2015 written by Kari T. Koskinen and has been published by Springer this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016-03-25 with Technology & Engineering categories.
This book comprises refereed papers from the 10th World Congress on Engineering Asset Management (WCEAM 2015), held in Tampere, Finland in September 2015. These proceedings include a compilation of state-of-the-art papers covering a comprehensive range of subjects equally relevant to business managers and engineering professionals alike. With a focus on various aspects of engineering asset management ranging from strategic level issues to detail-level machine health issues, these papers address both industry and public sector concerns and issues, as well as advanced academic research. Proceedings of the WCEAM 2015 is an excellent reference and resource for asset management practitioners, researchers and academics, as well as undergraduate and postgraduate students at tertiary institutions or in the industry.
Modeling And Simulation Of An Industrial Secondary Reformer Reactor
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Author : Ali Ashour AL-Dhfeery
language : en
Publisher:
Release Date : 2012
Modeling And Simulation Of An Industrial Secondary Reformer Reactor written by Ali Ashour AL-Dhfeery and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with categories.
Advanced Reactors Intermediate Heat Exchanger Ihx Coupling
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Author :
language : en
Publisher:
Release Date : 2016
Advanced Reactors Intermediate Heat Exchanger Ihx Coupling written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016 with categories.
The overall goal of the research project was to model the behavior of the advanced reactorintermediate heat exchange system and to develop advanced control techniques for off-normal conditions. The specific objectives defined for the project were: 1. To develop the steady-state thermal hydraulic design of the intermediate heat exchanger (IHX); 2. To develop mathematical models to describe the advanced nuclear reactor-IHX-chemical process/power generation coupling during normal and off-normal operations, and to simulate models using multiphysics software; 3. To develop control strategies using genetic algorithm or neural network techniques and couple these techniques with the multiphysics software; 4. To validate the models experimentally The project objectives were accomplished by defining and executing four different tasks corresponding to these specific objectives. The first task involved selection of IHX candidates and developing steady state designs for those. The second task involved modeling of the transient and offnormal operation of the reactor-IHX system. The subsequent task dealt with the development of control strategies and involved algorithm development and simulation. The last task involved experimental validation of the thermal hydraulic performances of the two prototype heat exchangers designed and fabricated for the project at steady state and transient conditions to simulate the coupling of the reactor- IHX-process plant system. The experimental work utilized the two test facilities at The Ohio State University (OSU) including one existing High-Temperature Helium Test Facility (HTHF) and the newly developed high-temperature molten salt facility.
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment
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Author : Jyeshtharaj Joshi
language : en
Publisher: Woodhead Publishing
Release Date : 2019-06-09
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment written by Jyeshtharaj Joshi and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-06-09 with Science categories.
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization