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ambe_emergent_neutrons

Geant4 simulation of AmBe emergent neutrons based on emergent neutrons simulation code for AmLi by J. Busenitz and R. Sazzad

awesome-nuclear

A curated list of open source projects used in nuclear science and engineering

benchmarks

Collection of models for reactor physics benchmarks

cad_to_openmc

code to target the conversion from a step-file to a h5m-geometry for neutronics

data

Collection of scripts for managing data for OpenMC

ersn-openmc

ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Bakkali & Tarek EL Bardouni, members of Radiation and Nuclear Systems Group ERSN at University Abdelmalek Essaady in Tetouan (Morocco).

fusion

GEANT4 simulation of a sealed tube neutron generator

geant4-ambe-source

AmBe Neutron Source in Geant4

geant4-neutron-detector

geant4_neutrones

Trabajo de Tesis

git_study

学习git

gitignore

A collection of useful .gitignore templates

he3_counter_tubes

example of simulation the thermal neutron counter by using GEANT4

he3detector

Geant4 projet for simulating ion tracked in He3 neutron detectors.

he3propcountersim

A geant4 program that simulates a ³He counter tube for thermal and epithermal neutron detection. Geant4 is a toolkit for the simulation of particle-matter interaction based on monte carlo simulations

mcnp_demo

msre

detailed cad model of the msre

nd1

a Geant4 Simulation of the response of liquid scintillator neutron Detector unit1 (nD1), as the first part simulation of my bachelor's thesis project at Tsinghua University in 2021

nda

a Geant4 Simulation of the response of liquid scintillator neutron Detector array (nDa), as the second part simulation of my bachelor's thesis project at Tsinghua University in 2021.

neutron-tracking-geant4

Tracking the interaction of neutrons with a silicon detector

neutron_length

geant4_neutron_length

neutronics-workshop

A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools

neutronlaboratory_shielding

GEANT4 application for simulation of DT- and DD- fusion neutron generators in an underground laboratory

njoy2016

Nuclear data processing with legacy NJOY

njoy21

NJOY for the 21st Century

onms

Open Neutron Multiplicity Simulation (ONMS) - Monte Carlo Simulation of Neutron Multiplicity Measurements based on Geant4

openmc

OpenMC Monte Carlo Code

openmc-notebooks

Example Jupyter notebooks for OpenMC

openmc_mcnp_adapter

Tool for converting MCNP input files to OpenMC classes/XML

passive_nns_with_gold-foil--response_function_generator

Geant4 based Monte-Carlo simulation application to generate the system response of a Passive NNS with gold foil