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  • Fusion Energy Neutronics Workshop

Installation options

  • Install with pip
  • Install with Conda
  • Install with Mamba
  • Install with Docker
  • Install optional extras
  • Install in the Cloud (binder)
  • Install in the cloud

Cross Sections

  • Task Introduction
  • Plotting isotope cross sections
  • Plotting element cross sections
  • Plotting material cross sections
  • Plotting Doppler broadened cross sections
  • Mean free path neutrons

Materials

  • Task Introduction
  • Making materials from isotopes
  • Making materials from elements
  • Making materials from a library
  • Changing materials
  • Mixing materials
  • Making materials from components

Making CSG Geometry

  • Task Introduction
  • Constructing simple CSG geometry
  • Constructing CSG geometry
  • 3D Geometry viewing

Making source terms

  • Task Introduction
  • Point source plotting
  • Ring source plotting
  • Plasma source plotting
  • Visualising Particle Tracks
  • Gamma sources
  • Unstructured mesh source
  • Structured mesh source

CSG cell TBR tally

  • Task Introduction
  • Performing Tritium Breeding Ratio (TBR) simulations
  • Simulating TBR as a function of Lithium enrichment

CSG cell DPA tally

  • Task Introduction
  • Simulating Displacements Per Atom (DPA)

CSG cell spectra tally

  • Task Introduction
  • Neutron flux and units
  • Plotting neutron energy spectra in a cell with progressively improved plotting and tallying techniques
  • Plotting neutron lethargy energy spectra across a surface with a energy group structure
  • Plotting photon and neutron energy spectra in a cell with a energy group structure
  • Plotting energy loss per collision

CSG cell mesh tally

  • Task Introduction
  • 2D mesh tallies
  • 3D mesh tallies
  • Cylinder mesh tallies

CSG cell instantaneous dose tally

  • Task Introduction
  • Simulations of effective dose on a surface
  • Simulations of effective dose as a function of distance
  • Simulate dose on a cell
  • Dose map from neutron pulse

Activation Transmutation Depletion

  • Task Introduction
  • Nuclide Build Up During Depletion Simulation
  • Tally Value Change During Depletion Simulation
  • Full pulse schedule depletion simulation

CSG shutdown dose tallies

  • Task Introduction
  • Shutdown dose rate D1S method
  • Shutdown dose rate D1S method different sources (DD+DT)

Volume Calculations

  • Task Introduction
  • Finding Volume of a Cell by sampling simulation.
  • Finding Volume of DAGMC Cell

Variance Reduction

  • Task Introduction
  • Survival Biasing Simulation
  • Variance Reduction - Weight Windows
  • Magic Method Iterative Weight Windows per run
  • Magic Method Iterative Weight Windows per Batch
  • FW CADIS Weight Windows

Making CAD geometry

  • Task Introduction
  • Making CAD with CadQuery
  • Making CAD geometry with Paramak

Converting CAD Geometry

  • Task Introduction
  • Converting CAD geometry to neutronics
  • CAD conversion in memory

Using DAGMC models in OpenMC

  • Task Introduction
  • Simple CAD model simulation
  • CAD model simulation with boundary tpyes
  • Making a hybrid CAD CSG model

CAD mesh fast flux simulation

  • Task Introduction
  • Simulation of fast neutron flux on unstructured mesh

CAD shutdown dose tallies

  • Task Introduction
  • Unstructured mesh R2S shutdown dose rate
  • Unstructured mesh R2S shutdown dose rate with different materials

Design study

  • Task Introduction
  • Design your own tokamak
  • Repository
  • Open issue

Index

By Jonathan Shimwell

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