A Computer Code, NATCON, for the Analyses of Steady-state Thermal-hydraulics and Safety Margins in Plate-type Research Reactors Cooled by Natural Convection PDF Download
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Author: R. S. Smith
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Languages : en
Pages : 37
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Author: R. S. Smith
Publisher:
ISBN:
Category :
Languages : en
Pages : 37
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Category : Power resources
Languages : en
Pages : 840
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Category : Power resources
Languages : en
Pages : 848
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Category : Nuclear energy
Languages : en
Pages : 24
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Category : Science
Languages : en
Pages : 1176
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Category : Government reports announcements & index
Languages : en
Pages : 1676
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Category :
Languages : en
Pages : 532
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Author: Masanori Kaminaga
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Languages : en
Pages : 40
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Languages : en
Pages :
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COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations: however, the transient capability has not yet been validated. This volume describes the finite-volume equations and the method used to solve these equations. It is directed toward the user who is interested in gaining a more complete understanding of these methods.
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Languages : en
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The STAT code was written to automate many of the steady-state thermal hydraulic safety calculations for the MIT research reactor, both for conversion of the reactor from high enrichment uranium fuel to low enrichment uranium fuel and for future fuel re-loads after the conversion. A Monte-Carlo statistical propagation approach is used to treat uncertainties in important parameters in the analysis. These safety calculations are ultimately intended to protect against high fuel plate temperatures due to critical heat flux or departure from nucleate boiling or onset of flow instability; but additional margin is obtained by basing the limiting safety settings on avoiding onset of nucleate boiling. STAT7 can simultaneously analyze all of the axial nodes of all of the fuel plates and all of the coolant channels for one stripe of a fuel element. The stripes run the length of the fuel, from the bottom to the top. Power splits are calculated for each axial node of each plate to determine how much of the power goes out each face of the plate. By running STAT7 multiple times, full core analysis has been performed by analyzing the margin to ONB for each axial node of each stripe of each plate of each element in the core.
