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Massively Parallel Cartesian Discrete Ordinates Method for Neutron Transport Simulation

Massively Parallel Cartesian Discrete Ordinates Method for Neutron Transport Simulation PDF Author: Salli Moustafa
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux inside the reactor core. This flux is modeled by the linear Boltzmann equation also called neutron transport equation. In this thesis, we focus on solving this equation using the discrete ordinates method (SN) on Cartesian mesh. This method involves a source iteration scheme including a sweep over the spatial mesh and gathering the vast majority of computations in the SN method. Due to the large amount of computations performed in the resolution of the Boltzmann equation, numerous research works were focused on the optimization of the time to solution by developing parallel algorithms for solving the transport equation. However, these algorithms were designed by considering a super-computer as a collection of independent cores, and therefore do not explicitly take into account the memory hierarchy and multi-level parallelism available inside modern super-computers. Therefore, we first proposed a strategy for designing an efficient parallel implementation of the sweep operation on modern architectures by combining the use of the SIMD paradigm thanks to C++ generic programming techniques and an emerging task-based runtime system: PaRSEC. We demonstrated the need for such an approach using theoretical performance models predicting optimal partitionings. Then we studied the challenge of converging the source iterations scheme in highly diffusive media such as the PWR cores. We have implemented and studied the convergence of a new acceleration scheme (PDSA) that naturally suits our Hybrid parallel implementation. The combination of all these techniques have enabled us to develop a massively parallel version of the SN Domino solver. It is capable of tackling the challenges posed by the neutron transport simulations and compares favorably with state-of-the-art solvers such as Denovo. The performance of the PaRSEC implementation of the sweep operation reaches 6.1 Tflop/s on 768 cores corresponding to 33.9% of the theoretical peak performance of this set of computational resources. For a typical 26-group PWR calculations involving 1.02×1012 DoFs, the time to solution required by the Domino solver is 46 min using 1536 cores.

Massively Parallel Cartesian Discrete Ordinates Method for Neutron Transport Simulation

Massively Parallel Cartesian Discrete Ordinates Method for Neutron Transport Simulation PDF Author: Salli Moustafa
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux inside the reactor core. This flux is modeled by the linear Boltzmann equation also called neutron transport equation. In this thesis, we focus on solving this equation using the discrete ordinates method (SN) on Cartesian mesh. This method involves a source iteration scheme including a sweep over the spatial mesh and gathering the vast majority of computations in the SN method. Due to the large amount of computations performed in the resolution of the Boltzmann equation, numerous research works were focused on the optimization of the time to solution by developing parallel algorithms for solving the transport equation. However, these algorithms were designed by considering a super-computer as a collection of independent cores, and therefore do not explicitly take into account the memory hierarchy and multi-level parallelism available inside modern super-computers. Therefore, we first proposed a strategy for designing an efficient parallel implementation of the sweep operation on modern architectures by combining the use of the SIMD paradigm thanks to C++ generic programming techniques and an emerging task-based runtime system: PaRSEC. We demonstrated the need for such an approach using theoretical performance models predicting optimal partitionings. Then we studied the challenge of converging the source iterations scheme in highly diffusive media such as the PWR cores. We have implemented and studied the convergence of a new acceleration scheme (PDSA) that naturally suits our Hybrid parallel implementation. The combination of all these techniques have enabled us to develop a massively parallel version of the SN Domino solver. It is capable of tackling the challenges posed by the neutron transport simulations and compares favorably with state-of-the-art solvers such as Denovo. The performance of the PaRSEC implementation of the sweep operation reaches 6.1 Tflop/s on 768 cores corresponding to 33.9% of the theoretical peak performance of this set of computational resources. For a typical 26-group PWR calculations involving 1.02×1012 DoFs, the time to solution required by the Domino solver is 46 min using 1536 cores.

Variational Nodal Transport Methods for Hexagonal and Three-dimensional Geometries. Final Report

Variational Nodal Transport Methods for Hexagonal and Three-dimensional Geometries. Final Report PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The properties of the variational nodal method for neutron transport calculations are investigated. The method is generalized for three-dimensional multigroup criticality problems in both hexagonal-z and Cartesian geometries. The method is implemented as part of the Argonne National Laboratory Code DIF3D, and applied to a series of benchmark reactor calculations. Variational nodal methods are compared of nodal transport methods based on both interface-current and discrete ordinate approximations. Model problems are used to examine the effect of running each of the three classes of nodal transport methods on computers with massively parallel architectures.

Variational Nodal Transport Methods for Hexagonal and Three-dimensional Geometries

Variational Nodal Transport Methods for Hexagonal and Three-dimensional Geometries PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The properties of the variational nodal method for neutron transport calculations are investigated. The method is generalized for three-dimensional multigroup criticality problems in both hexagonal-z and Cartesian geometries. The method is implemented as part of the Argonne National Laboratory Code DIF3D, and applied to a series of benchmark reactor calculations. Variational nodal methods are compared of nodal transport methods based on both interface-current and discrete ordinate approximations. Model problems are used to examine the effect of running each of the three classes of nodal transport methods on computers with massively parallel architectures.

A Quadratic-linear Nodal Discrete Ordinates Method for Neutron Transport in X,Y, Geometry

A Quadratic-linear Nodal Discrete Ordinates Method for Neutron Transport in X,Y, Geometry PDF Author: Tim D. Bohm
Publisher:
ISBN:
Category :
Languages : en
Pages : 330

Book Description


Solution of the Within-group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures

Solution of the Within-group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures PDF Author: Robert Joseph Zerr
Publisher:
ISBN:
Category :
Languages : en
Pages : 320

Book Description


The Discrete Ordinates Method for the Neutron Transport Equation in an Infinite Cylindrical Domain

The Discrete Ordinates Method for the Neutron Transport Equation in an Infinite Cylindrical Domain PDF Author: Mohammad Asadzadeh
Publisher:
ISBN:
Category :
Languages : en
Pages : 22

Book Description


An Analytical Nodal Discrete Ordinates Solution to the Transport Equation in Cartesian Geometry

An Analytical Nodal Discrete Ordinates Solution to the Transport Equation in Cartesian Geometry PDF Author: Joshua Rocheleau
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 88

Book Description
A novel Analytical Nodal Discrete Ordinates (ANDO) method for the solution of the discrete ordinates (SN) neutron transport equation in cartesian geometry is presented. A nodal method approximates the multi-dimensional transport equation as a system of coupled one-dimensional transport equations along each coordinate axis by transverse integration. The resulting transverse-integrated equations can then be discretized. The discretization utilized in the ANDO method is based on a recent closed-form analytical solution in slab geometry to give a truly closed-form solution on the computational cell. Further, the closed-form solution on any 2n heterogenous domain is also readily obtained. The new ANDO method is free from spatial truncation error within the computational cell and is limited in accuracy only by the approximation used for the transverse leakage, as are all analytical nodal methods. Results for constant, linear, and quadratic transverse leakage approximations are presented. The ANDO method possesses a number of favorable properties such as high accuracy, rapid convergence, asymptotic preserving, positivity preserving, near linear computational complexity, and is local-hp adaptive. It is also shown that the ANDO method can easily be extended to higher order transverse leakage approximations, to 3-dimensional cartesian geometry, and to multi-group.

An Even-parity/odd-parity Formulation for Deterministic Transport Calculations on Massively Parallel Computers

An Even-parity/odd-parity Formulation for Deterministic Transport Calculations on Massively Parallel Computers PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 10

Book Description
We have developed a highly parallel deterministic method for performing time-dependent particle (neutron, gamma-ray, or thermal radiation) transport calculations on arbitrarily connected 3-D tetrahedral meshes. The standard discrete-ordinates method, which is used to solve the first-order form of the transport equation, is extremely cumbersome to apply on such meshes and is based upon a mesh sweeping algorithm that is highly sequential in nature. A serial 1-D code for the CRAY-YMP and a parallel 1-D code for the CM-2 (Connection Machine) have been written to test our basic method. Comparisons between these two codes have shown that our new even/odd parity method is highly parallelizable. 10 refs., 2 figs.

Multidimensional Discrete Ordinates Transport on Massively Parallel Architectures

Multidimensional Discrete Ordinates Transport on Massively Parallel Architectures PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Discrete Ordinates Angular Quadrature of the Neutron Transport Equation

Discrete Ordinates Angular Quadrature of the Neutron Transport Equation PDF Author: Kaye D. Lathrop
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 52

Book Description