khurrumsaleem Goto Github PK

lbmfoam

My Nuclear Engineering Master thesis at Politecnico di Milano: development of an OpenFOAM solver for MSFR simulations employing Lattice Boltzmann Method

learn-me-fuel

Scripts for various machine learning implementations

lectures

Lectures for the course "Scientific Programming in Python" at Osnabrück University

libdetran

deterministic transport utilities

librom

Model reduction library with an emphasis on large scale parallelism and linear subspace methods

like-me-fuel

UW CHTC-enabled workflow for spent fuel predictions via a maximum likelihood calculation

linac

A platform for clinical linear accelerator simulation using GEANT4.

lra-holo-transients

A comparison of high-order/low-order transient techniques on the 2D LRA benchmark.

lwr_pincell_adaptivity

A repository to attempt to add adaptivity to the OpenMC-MOOSE coupled LWR Pincell example from the Cardinal Tutorials

macaw

MaCaw is a MOOSE-based application that enables domain-decomposed neutral particle transport calculations in MOOSE. It leverages the ray tracing MOOSE module for unstructured mesh tracking and OpenMC for collision physics, handling material definitions, and tallying quantities.

machine_learning_for_urr

6.867 Team Project

manatee

Monte Carlo / Sn / SP1 Transport

master-project

masters-thesis

A repository for my Master's thesis

materials-compendium

Python tools to process the PNNL Materials Compendium

matlab-transport-pack

Several MATLAB routines for performing neutron transport and reactor physics.

matlab_codes

Implementation in matlab of numerical methods applied in the neutron transport theory

matmcnp

A utility code for generating material cards for MCNP

matplotx

:bar_chart: More styles and useful extensions for Matplotlib

mc-hammer

3D Monte Carlo neutron transport

mc4kidz

Fun-to-watch demonstration monte carlo simulator

mcdc

MC/DC: Monte Carlo Dynamic Code

mcfeedback

Coupled Thermal-MC code to study feedback effects in Monte Carlo

mcfr

Design studies of molten chloride breeder reactor

mcfr-mcnp

In this work I designed and analyzed the core of a Molten Chloride Fast Reactor in MCNP6. The reactor was designed based off three parametric studies to obtain a critical reactor. The parameteric studies consisted of a fuel composition study, reactor geometry study, and vessel thickness study. Once an optimized critical reactor was designed, the te

mckeff

Monte Carlo neutron transport solver to solve for the effective multiplication factor in an innite lattice of reactor fuel pins with vacuum boundaries on top and bottom.

mckit

A tool for flattening MCNP models

mcnp-input-reader

The package for reading mcnp input in a pythonic way

mcxcl

Monte Carlo eXtreme for OpenCL (MCXCL)

meitner-task-2

Holds simulation results, notes, documentation, and publications related to the ARFC MEITNER Project, Task 2 (Fuel Cycle modeling and simulation for TAP MSR).