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Transient Analysis For The High Temperature Pebble Bed Reactor Coupled To The Energy Conversion System


Transient Analysis For The High Temperature Pebble Bed Reactor Coupled To The Energy Conversion System
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Transient Analysis For The High Temperature Pebble Bed Reactor Coupled To The Energy Conversion System


Transient Analysis For The High Temperature Pebble Bed Reactor Coupled To The Energy Conversion System
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Author : E. C. Verkerk
language : en
Publisher:
Release Date : 1998

Transient Analysis For The High Temperature Pebble Bed Reactor Coupled To The Energy Conversion System written by E. C. Verkerk and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1998 with categories.




Analysis Of Transients And Control Of Advanced High Temperature Reactor Coupled Heat Exchangers System


Analysis Of Transients And Control Of Advanced High Temperature Reactor Coupled Heat Exchangers System
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Author : Isaac James Skavdahl
language : en
Publisher:
Release Date : 2016

Analysis Of Transients And Control Of Advanced High Temperature Reactor Coupled Heat Exchangers System written by Isaac James Skavdahl and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016 with Nuclear reactors categories.


Control of advanced reactor system consisting of a nuclear reactor, an intermediate heat exchanger (IHX), and a secondary heat exchanger (SHX) is investigated in this research. Initial transient analysis of the system was conducted using commercially available process simulation softwares PRO-II and DYNSIM. System parameters of significance--controlled and manipulated variables--were identified, and a control strategy was developed to maintain the controlled variables at their set points. The system response was simulated for various load disturbances, initially for the coupled heat exchangers system, followed by incorporation of the reactor dynamics in the system. Alternate strategies to control the temperature entering the process or power conversion unit (PCU) by either manipulating the secondary loop flow rate, controlling reactor power, or a combination of the two methods were investigated. Combining both methods of control showed great utility in controlling the temperature entering the process and may be an ideal method for control.



Coupling Of Cynod And Relap5 For Pebble Bed Reactor Transient Analysis


Coupling Of Cynod And Relap5 For Pebble Bed Reactor Transient Analysis
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Author : Michael Keith Oliver
language : en
Publisher:
Release Date : 2010

Coupling Of Cynod And Relap5 For Pebble Bed Reactor Transient Analysis written by Michael Keith Oliver and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with Dissertations, Academic categories.




Cynod


Cynod
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Author :
language : en
Publisher:
Release Date : 2008

Cynod written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2008 with categories.


The Pebble Bed Reactor (PBR) is one of the two concepts currently considered for development into the Next Generation Nuclear Plant (NGNP). This interest is due, in particular, to the concept's inherent safety characteristics. In order to verify and confirm the design safety characteristics of the PBR computational tools must be developed that treat the range of phenomena that are expected to be important for this type of reactors. This paper presents a recently developed 2D R-Z cylindrical nodal kinetics code and shows some of its capabilities by applying it to a set of known and relevant benchmarks. The new code has been coupled to the thermal hydraulics code THERMIX/KONVEK[1] for application to the simulation of very fast transients in PBRs. The new code, CYNOD, has been written starting with a fixed source solver extracted from the nodal cylindrical geometry solver contained within the PEBBED code. The fixed source solver was then incorporated into a kinetic solver. The new code inherits the spatial solver characteristics of the nodal solver within PEBBED. Thus, the time-dependent neutron diffusion equation expressed analytically in each node of the R-Z cylindrical geometry sub-domain (or node) is transformed into one-dimensional equations by means of the usual transverse integration procedure. The one-dimensional diffusion equations in each of the directions are then solved using the analytic Green's function method. The resulting equations for the entire domain are then re-cast in the form of the Direct Coarse Mesh Finite Difference (D-CMFD) for convenience of solution. The implicit Euler method is used for the time variable discretization. In order to correctly treat the cusping effect for nodes that contain a partially inserted control rod a method is used that takes advantage of the Green's function solution available in the intrinsic method. In this corrected treatment, the nodes are re-homogenized using axial flux shapes reconstructed based on the Green's function method. The performance of the new code is demonstrated by applying it to a delayed supercritical problem and a to the OECD PBMR400 rod ejection benchmark problem. The latter makes use of the coupled CYNOD-THERMIX/KONVEK codes. A final improvement to the code is the subject of a companion paper: a heterogeneous TRISO fuel particle model was devised and incorporated into the code and used to provide an enhanced Doppler treatment. The new code is currently being coupled to the RELAP5-3D code for thermal-hydraulics. The full length paper will include extensive summaries of the equations and algorithm, descriptions of the sample and benchmark problems and details of the results. It is shown, in inter-code comparisons, that the new code correctly predicts the transient behaviors of the test problems.



Nuclear Science Abstracts


Nuclear Science Abstracts
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Author :
language : en
Publisher:
Release Date : 1976-02

Nuclear Science Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1976-02 with Nuclear energy categories.




Multiphase Flow And Heat Transfer In Pebble Bed Reactor Core


Multiphase Flow And Heat Transfer In Pebble Bed Reactor Core
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Author : Shengyao Jiang
language : en
Publisher: Springer Nature
Release Date : 2020-11-19

Multiphase Flow And Heat Transfer In Pebble Bed Reactor Core written by Shengyao Jiang and has been published by Springer Nature this book supported file pdf, txt, epub, kindle and other format this book has been release on 2020-11-19 with Science categories.


This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.



Optimized Core Design And Fuel Management Of A Pebble Bed Type Nuclear Reactor


Optimized Core Design And Fuel Management Of A Pebble Bed Type Nuclear Reactor
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Author : Brian Boer
language : en
Publisher:
Release Date : 2008

Optimized Core Design And Fuel Management Of A Pebble Bed Type Nuclear Reactor written by Brian Boer and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2008 with Nuclear fuels categories.


The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.



Erda Energy Research Abstracts


Erda Energy Research Abstracts
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Author : United States. Energy Research and Development Administration. Technical Information Center
language : en
Publisher:
Release Date : 1977

Erda Energy Research Abstracts written by United States. Energy Research and Development Administration. Technical Information Center and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1977 with Force and energy categories.




Erda Energy Research Abstracts


Erda Energy Research Abstracts
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Author :
language : en
Publisher:
Release Date : 1977

Erda Energy Research Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1977 with categories.




Energy Research Abstracts


Energy Research Abstracts
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Author :
language : en
Publisher:
Release Date : 1984

Energy Research Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1984 with Power resources categories.