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VVER 1000 reactor simulation with mcnp

VVER 1000 reactor core was simulated with MCNPX and the input file was prepared for sequence usage in the project.  VVER reactor or WWER reactor (abbreviated as Water-Water Energetic Reactor) is a series of light

Introduction, Download, and Installation Guide for MCNP Software Versions 4C, 5, X2.6

Introduction, Download, and Installation Guide for MCNP Software Versions 4C, 5, X2.6 MCNP software is a Monte Carlo program that has been developed by the Los Alamos National Laboratory since 1957. This software uses Monte

Conversion of Mesh Tally Using Gridconv from MCNP Output + Software Requirements

In the realm of scientific and technical simulations, the Monte Carlo method is heralded as a powerful tool for the analysis and modeling of intricate processes. Among the diverse instruments utilized in this method, mesh

MCNP Tally Segment catd - FS

In the calculation of tallies using the MCNP Monte Carlo code, the desired results are obtained using tallies. If we want to calculate tally results from different layers of the desired target, two methods can

Mastering SPECT Simulations with MCNP: A Comprehensive Guide

 Dive into the world of Single Photon Emission Computed Tomography (SPECT) with this comprehensive course designed to elevate your understanding and proficiency in using the Monte Carlo N-Particle Transport Code (MCNP). This course covers the

How to draw isodose curve from the MCNP program?

What is an isodose curve? An isodose diagram for a given beam consists of a family of isodose curves, usually plotted with an increasing depth dose percentage. It shows the change in dose as a

Download MCNP6.2 software, the latest and most complete version of MCNP software

Download MCNP6.2 software, the latest and most complete version of MCNP software Monte Carlo N-Particle or MCNP®1 is a general-purpose Monte Carlo radiative transfer code designed to track many types of particles over a wide

download mcnp book material data usefull for simulation

Meaningful simulations of radiation transport applications require realistic definitions of material composition and densities. When seeking that information for applications in fields such as homeland security, radiation shielding and protection, and criticality safety, researchers usually

Tutorial on adding phantom to pre-written MCNP program

Tutorial on adding phantom to pre-written MCNP program Table of Contents introduction Educational video introduction Download the MCNP phantom code program in the clinical accelerator 2100 using the principles of writing and adding phantoms to

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