Nodal Methods For Solving The Diffusion Equation For Fast Reactor Analysis
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Nodal Methods For Solving The Diffusion Equation For Fast Reactor Analysis
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Author : J. M. Putney
language : en
Publisher:
Release Date : 1984
Nodal Methods For Solving The Diffusion Equation For Fast Reactor Analysis written by J. M. Putney and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1984 with categories.
Nodal Method For Fast Reactor Analysis
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Author :
language : en
Publisher:
Release Date : 1979
Nodal Method For Fast Reactor Analysis written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with categories.
In this paper, a nodal method applicable to fast reactor diffusion theory analysis has been developed. This method has been shown to be accurate and efficient in comparison to highly optimized finite difference techniques. The use of an analytic solution to the diffusion equation as a means of determining accurate coupling relationships between nodes has been shown to be highly accurate and efficient in specific two-group applications, as well as in the current multigroup method.
Three Dimensional Nodal Diffusion And Transport Methods For The Analysis Of Fast Reactor Critical Experiments
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Author :
language : en
Publisher:
Release Date : 1984
Three Dimensional Nodal Diffusion And Transport Methods For The Analysis Of Fast Reactor Critical Experiments 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 categories.
This paper describes two new nodal methods for solving the multigroup neutron diffusion and transport equations in three-dimensional Cartesian geometry. These methods have been developed for the global analysis of fast-reactor critical experiments once cell-averaged multigroup cross sections for each matrix position or drawer have been computed using appropriate cell-homogenization procedures. Brief descriptions of the nodal diffusion and transport schemes are presented, along with results of two- and three-dimensional calculations for a current Zero Power Plutonium Reactor (ZPPR) configuration.
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Quarterly Technical Progress Report April 1 June 30 2000
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Author :
language : en
Publisher:
Release Date : 2000
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Quarterly Technical Progress Report April 1 June 30 2000 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2000 with categories.
The status summary of Nuclear Energy Research Initiative (NERI) Tasks - Phase 1 are: Task 1--The development of the following methods in 1D slab geometry: (1) Homogenization and definition of discontinuity factors, (2) Group constants functionalization using assembly transport solution of multigroup eigenvalue problem with albedo boundary conditions, and (3) solving coarse-mesh effective few-group 1D QD moment equations using tables of data parameterized with respect to the ratio {rvec n} · {rvec J}{sup G}/{tilde {phi}{sup G}} on boundaries. Status summary of NERI Tasks - Phase 1: Task 2--Development of a numerical method for solving the 2D few-group moment QD equations: (1) Development of a nodal discretization method for 2D moment QD equations, and (2) Development of an efficient iteration method for solving the system of equations of the nodal discretization method for 2D moment QD equations.
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Nuclear Energy Research Initiative Neri Program Quarterly Technical Progress Report
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Author :
language : en
Publisher:
Release Date : 2000
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Nuclear Energy Research Initiative Neri Program Quarterly Technical Progress Report written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2000 with categories.
Status Summary of NERI Tasks - Phase 1 - Task 1. The development of the following methods in ID slab geometry: (1) Homogenization and definition of discontinuity factors, (2) Group constants functionalization using assembly transport solution of multigroup eigenvalue problem with albedo boundary conditions, and (3) Solving coarse-mesh effective few-group 1D QD moment equations using tables of data parameterized with respect to the ratio {rvec n} · {bar J}{sup G}/{bar {phi}}{sup G} on boundaries. Status Summary of NERI Tasks - Phase 1 - Task 2. Development of a numerical method for solving the 2D few-group moment QD equations: (1) Development of a nodal discretization method for 2D moment QD equations, and (2) Development of an efficient iteration method for solving the system of equations of the nodal discretization method for 2D moment QD equations.
Proceedings Of The Topical Meeting On Computational Methods In Nuclear Engineering
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Author :
language : en
Publisher:
Release Date : 1979
Proceedings Of The Topical Meeting On Computational Methods In Nuclear Engineering written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with Nuclear engineering categories.
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Nuclear Energy Research Initiative Neri Program Quarterly Technical Progress Report July 1 September 30 2000
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Author :
language : en
Publisher:
Release Date : 2000
An Innovative Reactor Analysis Methodology Based On A Quasidiffusion Nodal Core Model Nuclear Energy Research Initiative Neri Program Quarterly Technical Progress Report July 1 September 30 2000 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2000 with categories.
Status Summary of Nuclear Energy Research Initiative (NERI) Tasks: Task 1--The development of the following methods in ID slab geometry: (1) Homogenization and definition of discontinuity factors, (2) Group constants functionalization using assembly transport solution of multigroup eigenvalue problem with albedo boundary conditions, and (3) Solving coarse-mesh effective few-group 1D QD moment equations using tables of data parametrized with respect to the ratio {rvec n} · {rvec {tilde J}{sup G}}/{tilde {phi}{sup G}} on boundaries. Task 2--Development of a numerical method for solving the 2D few-group moment QD equations: (1) Development of a nodal discretization method for 2D moment QD equations, and (2) Development of an efficient iteration method for solving the system of equations of the nodal discretization method for 2D moment QD equations. Task 3--The development of the following methods in 2D X-Y geometry: (1) homogenization and definition of discontinuity factors, (2) group constants functionalization using assembly transport solution of multigroup eigenvalue problem with albedo boundary conditions, and (3) solving coarse-mesh effective few-group QD moment equations using tables of data parametrized with respect to the ratio {rvec n} · {rvec {tilde J}{sup G}}/{tilde {phi}{sup G}} on boundaries. Task 4--Development of a numerical method for solving the few-group moment QD equations in 3D geometry: (1) Development of a nodal method for discretization of 3D moment QD equations, and (2) Development of an efficient iteration method for solving the system of nodal discretized equations of moment QD equations in 3D geometry.
Reactor Dosimetry State Of The Art 2008 Proceedings Of The 13th International Symposium
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Author : Wim Voorbraak
language : en
Publisher: World Scientific
Release Date : 2009-08-19
Reactor Dosimetry State Of The Art 2008 Proceedings Of The 13th International Symposium written by Wim Voorbraak and has been published by World Scientific this book supported file pdf, txt, epub, kindle and other format this book has been release on 2009-08-19 with Science categories.
This book gives the state of the art in the field of reactor dosimetry as applied in nuclear power plants and research reactors. Surveillance programs are presented for nuclear power plants in Europe, including Russia and Ukraine, USA, Argentina and Korea. New cross-section measurements from most of the European, American and Japanese research reactors are reported. The latest developments in computer code development for radiation transport and shielding calculations, and radiation measurement techniques are also highlighted.
Neutronics Methods For Transient And Safety Analysis Of Fast Reactors
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Author : Marchetti, Marco
language : en
Publisher: KIT Scientific Publishing
Release Date : 2017-03-02
Neutronics Methods For Transient And Safety Analysis Of Fast Reactors written by Marchetti, Marco and has been published by KIT Scientific Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017-03-02 with categories.
Progress In Nuclear Energy
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Author :
language : en
Publisher:
Release Date : 1986
Progress In Nuclear Energy written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with Nuclear energy categories.