Computational Methods in Chemical Engineering (UMass Lowell, Spring 2024); Prof. Valmor F. de Almeida.
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Updated
May 8, 2024 - Jupyter Notebook
Computational Methods in Chemical Engineering (UMass Lowell, Spring 2024); Prof. Valmor F. de Almeida.
An open-source nuclear reactor analysis automation framework that helps design teams increase efficiency and quality
Compilation of thermo-physical properties for lead/bismuth-based liquid metals for fast reactor technology
Qualitative & quantitative performance evaluation of traditional image processing and CNN based automatic methods on Pool Boiling IR images of MIT’s Nuclear Reactor Lab by measuring important boiling heat transfer parameters statistically. Work performed in 2019 as part of BSc. Thesis.
A multi isotope enrichment module for the nuclear fuel cycle simulator Cyclus
Holds the research group website.
This notebook demonstrates the process of running calculations for the Molten Salt Reactor Experiment (MSRE) directly from a Computer-Aided Design (CAD) drawing.
A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
A visualization of US Navy Nuclear Capacity compared to the US civilian reactor fleet
Input files for ARMI representing the Fast Flux Test Facility isothermal benchmark cases from INL/EXT-09-16524
NuSD is a Geant4-based simulation framework developed to perform simulation studies on various segmented scintillation detectors.
This a a recreation of the RBMK-1000 reactor from Chernobyl: the legacy continues.
Nuclear thermal space propulsion & control systems simulation game prototype.
Further development has been moved to: https://github.com/danjkim21/adv-nuclear-reactor-api-v2
This GUI and terminal based program attempts to analyze both qualitative and quantitative characteristics of nuclear reactors. Currently can be done in GUI or in terminal. GUI tkinter is unable to conduct analysis on qualitative characteristics and does not have a scroll bar (two things I was unable to complete).
Analysis of the experimental results of the neutron flow in a subcritical nuclear reactor (in Greek).
Tally table is a simple GUI program which extracts user defined tallies from a MCNP output.
A simple, unscientific nuclear reactor simulation.
MScA project
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