The ORIGEN 2 code is established as a standard tool for calculating isotope generation and depletion in nuclear reactors. The success of this code is entirely dependent on the accuracy and completeness of its nuclear
CHAPTER 1: INTRODUCTION ORIGEN Code Evolution and Updates Purpose and Scope of ORIGEN2 Report Organization Overview CHAPTER 2: GENERAL CONSIDERATIONS ORIGEN2 MAIN Routine Functions Variable Dimensioning System Free-Format Input Rules Command Concept Implementation Vector Organization (Output
Geant4 Tutorial: Particle Types and Macro File Usage 🎓 Geant4 Training Series – Particle Definitions and Macro File Syntax In this part of the Geant4 training series by Partoyar Academy, we explore one of the
Introduction to GAMOS: A Geant4-Based Framework for Medicine-Oriented Simulations Overview GAMOS, short for Geant4-based Architecture for Medicine-Oriented Simulations, is a Monte Carlo simulation framework built upon the powerful Geant4 toolkit. Designed with both simplicity and
Within the ecosystem of MCNP, a leading software package for simulating nuclear processes, makxsf.exe is a vital pre-processing tool. Its name stands for "Make Cross-Section File," and it is responsible for generating the specialized nuclear data libraries
Structured Learning at Partoyar Academy: A Systematic Path to Mastery in Nuclear Computation Introduction Partoyar Academy was founded with a clear mission: to deliver specialized, application-driven education in the complex and critical field of nuclear
The Molten-Salt Reactor Experiment (MSRE) was a pioneering nuclear reactor project conducted at Oak Ridge National Laboratory (ORNL) in the United States from 1965 to 1969. It aimed to demonstrate the feasibility of molten-salt reactors
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The right-hand coordinate system is used in Monte Carlo computing systems. Understanding this coordinate helps to get the right imaginations in 3D modeling. In this article, the most important points that are necessary when working
In Dependent source, Depending on the source parameter, the value of one parameter is different for different particles. For example, if the source emits 2 different radiation and each of these two radiations has a specific
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
How to Calculate Weight Percentages for Different Compounds in MCNP: A Comprehensive Guide Introduction In the world of nuclear simulations, the MCNP code is recognized as one of the most powerful computational tools. One of the most
The dxtran transportation method is a mandatory sampling method that is presented and used in the Monte Carlo MCNP code to increase the probability of sampling in one place. In this article, we have fully
Purchasing from Partoyar Academy website is a simple and easy process, but nevertheless, the user may encounter questions when using it, which is tried to be explained here. Table of Contents 1) Shopping guide 1-1)
Nuclear Code Fork is a computer code for calculating the stable, thermo-mechanical behavior of oxide fuel rods in long-term fuel. Reliable prediction of the behavior of nuclear fuel rods of nuclear power reactors, the basic
Interfile is a standardized file format primarily used in the field of nuclear medicine to facilitate the exchange of imaging data and associated information between different systems and software. Here are some key points about Interfile:
Geant4 (Geometry and Tracking) is a powerful and versatile toolkit used for the simulation of the passage of particles through matter. It is widely used in high-energy physics, astrophysics, and medical physics. Developed by the
EMPIRE Nuclear Reaction Code: A Comprehensive Framework for Modeling and Cross-Section Calculations in Intermediate to High Energy Regimes Introduction In the realm of nuclear science and engineering, accurate modeling of nuclear reactions is essential for
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