Two programming models for parallelizing the Angular Domain Decomposition (ADD) of the discrete ordinates (S{sub n}) approximation of the neutron transport equation are examined. These are the shared memory model based on the POSIX threads (Pthreads) standard, and the message passing model based on the Message Passing Interface (MPI) standard. These standard libraries are available on most multiprocessor platforms thus making the resulting parallel codes widely portable. The question is: on a fixed platform, and for a particular code solving a given test problem, which of the two programming models delivers better parallel performance? Such comparison is possible on Symmetric Multi-Processors (SMP) architectures in which several CPUs physic...
Mathematical simulation of fast neutron reactors requires high-precision calculations of protection ...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
With the increase in computational resources, parallel computation in neutron transport codes is inh...
The PIDOTS neutral particle transport code utilizes a red/black implementation of the Parallel Gauss...
By programming in parallel, large problem is divided in smaller ones, which are solved concurrently....
The effect of three communication schemes for solving Arbitrarily High Order Transport (AHOT) method...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Click on the DOI link to access the article (may not be free).The advancement of multicore systems d...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The shift toward multicore architectures has ushered in a new era of shared memory parallelism for s...
We present performance results obtained on a 128-node Cray Research T3D computer by a neutron transp...
APOLLO3® and TRIPOLI-4® are registered trademark of CEAInternational audienceIn this paper we analyz...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
International audienceThis paper studies the influence of various parameters, in order to improve th...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Mathematical simulation of fast neutron reactors requires high-precision calculations of protection ...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
With the increase in computational resources, parallel computation in neutron transport codes is inh...
The PIDOTS neutral particle transport code utilizes a red/black implementation of the Parallel Gauss...
By programming in parallel, large problem is divided in smaller ones, which are solved concurrently....
The effect of three communication schemes for solving Arbitrarily High Order Transport (AHOT) method...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Click on the DOI link to access the article (may not be free).The advancement of multicore systems d...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The shift toward multicore architectures has ushered in a new era of shared memory parallelism for s...
We present performance results obtained on a 128-node Cray Research T3D computer by a neutron transp...
APOLLO3® and TRIPOLI-4® are registered trademark of CEAInternational audienceIn this paper we analyz...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
International audienceThis paper studies the influence of various parameters, in order to improve th...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Mathematical simulation of fast neutron reactors requires high-precision calculations of protection ...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
With the increase in computational resources, parallel computation in neutron transport codes is inh...