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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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Book Synopsis 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 by :
Download or read book 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 published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model. Nuclear Energy Research Initiative (NERI) Program. Quarterly Technical Progress Report by :
Download or read book 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 published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model. Quarterly Technical Progress Report, April 1 - June 30, 2000 by :
Download or read book An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model. Quarterly Technical Progress Report, April 1 - June 30, 2000 written by and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model. Topical Report by :
Download or read book An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model. Topical Report written by and published by . This book was released on 2000 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is a topical report of the NERI project ''An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model''
Download or read book Final Report, NERI Project written by and published by . This book was released on 2003 with total page 101 pages. Available in PDF, EPUB and Kindle. Book excerpt: OAK (B204) Final Report, NERI Project: ''An Innovative Reactor Analysis Methodology Based on a Quasidiffusion Nodal Core Model'' The present generation of reactor analysis methods uses few-group nodal diffusion approximations to calculate full-core eigenvalues and power distributions. The cross sections, diffusion coefficients, and discontinuity factors (collectively called ''group constants'') in the nodal diffusion equations are parameterized as functions of many variables, ranging from the obvious (temperature, boron concentration, etc.) to the more obscure (spectral index, moderator temperature history, etc.). These group constants, and their variations as functions of the many variables, are calculated by assembly-level transport codes. The current methodology has two main weaknesses that this project addressed. The first weakness is the diffusion approximation in the full-core calculation; this can be significantly inaccurate at interfaces between different assemblies. This project used the nodal diffusion framework to implement nodal quasidiffusion equations, which can capture transport effects to an arbitrary degree of accuracy. The second weakness is in the parameterization of the group constants; current models do not always perform well, especially at interfaces between unlike assemblies. The project developed a theoretical foundation for parameterization and homogenization models and used that theory to devise improved models. The new models were extended to tabulate information that the nodal quasidiffusion equations can use to capture transport effects in full-core calculations.
Book Synopsis Continued Development of Nodal Methods for Reactor Analysis by : Allan F. Henry
Download or read book Continued Development of Nodal Methods for Reactor Analysis written by Allan F. Henry and published by . This book was released on 1985 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt:
