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MCNP Monte Carlo tutorial from zero to hero

Introduction to MCNP Monte Carlo N-Particle Transport (MCNP) is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation transport code designed to track many particle types over broad ranges of energies and is developed by Los
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180 $

geant4 video zero to hero

geant4 video sero to hero Table of Contents content 1) installing Geant4 2) linux basic command,  3) geant4 general command 4) geaomerty 5) source 6) tracking 7)physicslist 8)ourput 1 9) scoring 10)root content 1) installing
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talys nuclear model code system film download

1.  NAME AND TITLE  TALYS 1.2 the  Nuclear Model Code System was developed for analysis and prediction of nuclear reactions and generation of nuclear data. Table of Contents 1.  NAME AND TITLE 2.  CONTRIBUTORS 3. 
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