This talk summarizes the main aspects of the LANL ASCI Eolus project and its major unclassified code project, MCNP. The MCNP code provide a state-of-the-art Monte Carlo radiation transport to approximately 3000 users world-wide. Almost all hardware platforms are supported because we strictly adhere to the FORTRAN-90/95 standard. For parallel processing, MCNP uses a mixture of OpenMp combined with either MPI or PVM (shared and distributed memory). This talk summarizes our experiences on various platforms using MPI with and without OpenMP. These platforms include PC-Windows, Intel-LINUX, BlueMountain, Frost, ASCI-Q and others
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron ...
We have developed an implicit Monte Carlo neutron transport code in C++ using the Parallel Object-Or...
The Eolus ASCI project includes parallel, 3-D transport simulation for various nuclear applications....
MCBEND is a general purpose radiation transport Monte Carlo code from AMEC Foster Wheelers’s ANSWERS...
We have parallelized a Monte Carlo photon transport algorithm. Three different parallel versions of ...
We have parallelized a Monte Carlo algorithm that simulates photon transport in an inertially confi...
The Monte Carlo radiation transport code MCNP has been successfully ported to two 64-bit workstation...
MCNPX is a Fortran 90 Monte Carlo radiation transport computer code that transports all particles at...
Version 4A of the Monte Carlo neutron, photon, and electron transport code MCNP, developed by LANL (...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
This paper contains two parts revolving around Monte Carlo transport simulation on Intel Many Integr...
The Monte Carlo transport workhorse, MCNP, is undergoing a massive renovation at Los Alamos National...
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently ...
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron ...
We have developed an implicit Monte Carlo neutron transport code in C++ using the Parallel Object-Or...
The Eolus ASCI project includes parallel, 3-D transport simulation for various nuclear applications....
MCBEND is a general purpose radiation transport Monte Carlo code from AMEC Foster Wheelers’s ANSWERS...
We have parallelized a Monte Carlo photon transport algorithm. Three different parallel versions of ...
We have parallelized a Monte Carlo algorithm that simulates photon transport in an inertially confi...
The Monte Carlo radiation transport code MCNP has been successfully ported to two 64-bit workstation...
MCNPX is a Fortran 90 Monte Carlo radiation transport computer code that transports all particles at...
Version 4A of the Monte Carlo neutron, photon, and electron transport code MCNP, developed by LANL (...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
This paper contains two parts revolving around Monte Carlo transport simulation on Intel Many Integr...
The Monte Carlo transport workhorse, MCNP, is undergoing a massive renovation at Los Alamos National...
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently ...
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron ...
We have developed an implicit Monte Carlo neutron transport code in C++ using the Parallel Object-Or...