A Computational Model for Convective, Conductive and Radiative Heat Transfer in High Power Density Gas Cooled and Gaseous Core Nuclear Reactors PDF Download
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Author: Gary G. Chen
Publisher:
ISBN:
Category :
Languages : en
Pages : 398
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Book Description
Author: Gary G. Chen
Publisher:
ISBN:
Category :
Languages : en
Pages : 398
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 124
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Author:
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Category : Nuclear energy
Languages : en
Pages : 1142
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Author:
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Category : Aeronautics
Languages : en
Pages : 1040
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Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
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Category :
Languages : en
Pages : 36
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Book Description
The new generation of nuclear reactors includes designs that are significantly different from light water reactors. Among these new reactor designs is the Modular High-Temperature Gas-Cooled Reactor (MHTGR). In addition, nuclear thermal rockets share a number of similarities with terrestrial HTGRs and would be amenable to similar types of analyses. In these reactors, the heat transfer in the solid core mass is of primary interest in design and safety assessment. One significant safety feature of these reactors is the capability to withstand a loss of pressure and forced cooling in the primary system and still maintain peak fuel temperatures below the safe threshold for retaining the fission products. To accurately assess the performance of gas-cooled reactors during these types of transients, a Helium/Hydrogen Cooled Reactor Analysis (HERA) computer code has been developed. HERA has the ability to model arbitrary geometries in three dimensions, which allows the user to easily analyze reactor cores constructed of prismatic graphite elements. The code accounts for heat generation in the fuel, control rods and other structures; conduction and radiation across gaps; convection to the coolant; and a variety of boundary conditions. The numerical solution scheme has been optimized for vector computers, making long transient analyses economical. Time integration is either explicit or implicit, which allows the use of the model to accurately calculate both short- or long-term transients with an efficient use of computer time. Both the basic spatial and temporal integration schemes have been benchmarked against analytical solutions. Also, HERA has been used to analyze a depressurized loss of forced cooling transient in a HTGR with a very detailed three-dimensional input model. The results compare favorably with other means of analysis and provide further validation of the models and methods. 18 refs., 11 figs.
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Category : Power resources
Languages : en
Pages : 806
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Author: United States. Superintendent of Documents
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Category : Government publications
Languages : en
Pages : 1214
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Author:
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Category : Nuclear energy
Languages : en
Pages : 1004
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Author: Raymond Todd Klann
Publisher:
ISBN:
Category :
Languages : en
Pages : 294
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Author: Shengyao Jiang
Publisher: Springer Nature
ISBN: 9811595658
Category : Science
Languages : en
Pages : 510
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Book Description
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.
