Abstract: New version of program package PARSE assigned for the transport calculations of neutral and charged particles in three-dimensional geometry by the Monte-Carlo method is described in this work. The program package allows to model formation of a neutron source by a beam of accelerated protons of hybrid systems, to calculate the energy spectrums of particles, energy release and other characteristics of the nucleon-nuclear cascade. The multi-group representation of the transport equation in the supposition of continuous slowing down of charged particles and the model of disastrous collisions are used.Note: Research direction:Programming, parallel computing, multimedi
An update on the development and validation of the MERCURY Monte Carlo particle transport code is pr...
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a unifo...
After a summary description of the theory of elastic collisions of nucleons with atoms, we present t...
ilbstract A review of methods developed for solution of particle transport problem is made. These ar...
Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and el...
Attention is focused on the application of the Monte Carlo method to particle transport problems, wi...
The Eolus ASCI project includes parallel, 3-D transport simulation for various nuclear applications....
The Monte Carlo (MC) method has been traditionally applied in nuclear design and analysis due to its...
This book focusses on the state of the art of Monte Carlo methods in radiation physics and particle ...
Charged particles of species different from the major constituents of a plasma might not reach local...
MC++ is an implicit multi-group Monte Carlo neutron transport code written in C++ and based on the P...
A scalable, parallel code system to perform neutral particle transport calculations in three dimensi...
Modern Monte Carlo radiation transport codes can be applied to model most applications of radiation,...
A new deterministic three-dimensional neutral and charged particle transport code, MultiTrans, has b...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
An update on the development and validation of the MERCURY Monte Carlo particle transport code is pr...
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a unifo...
After a summary description of the theory of elastic collisions of nucleons with atoms, we present t...
ilbstract A review of methods developed for solution of particle transport problem is made. These ar...
Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and el...
Attention is focused on the application of the Monte Carlo method to particle transport problems, wi...
The Eolus ASCI project includes parallel, 3-D transport simulation for various nuclear applications....
The Monte Carlo (MC) method has been traditionally applied in nuclear design and analysis due to its...
This book focusses on the state of the art of Monte Carlo methods in radiation physics and particle ...
Charged particles of species different from the major constituents of a plasma might not reach local...
MC++ is an implicit multi-group Monte Carlo neutron transport code written in C++ and based on the P...
A scalable, parallel code system to perform neutral particle transport calculations in three dimensi...
Modern Monte Carlo radiation transport codes can be applied to model most applications of radiation,...
A new deterministic three-dimensional neutral and charged particle transport code, MultiTrans, has b...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
An update on the development and validation of the MERCURY Monte Carlo particle transport code is pr...
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a unifo...
After a summary description of the theory of elastic collisions of nucleons with atoms, we present t...