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Code for automated production of a fusion materials activation handbook using OpenMC. Containing simulated activity, dose and decay heat characteristics for elements and materials exposed to neutron irradiation.

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fusion_activation_handbook

Code for automated production of a fusion materials activation handbook using OpenMC.

The handbook contains the following simulated values on a wide range of elements and materials exposed to neutron irradiation.

  • Simulated activity
  • Atom inventory
  • Dose
  • Decay heat

Download the latest PDF report [here](link to latest release)

To reproduce the handbook locally

1. Install OpenMC and other dependencies

From a conda environment you can install the OpenMC

conda install -c conda-forge openmc==0.13.3
pip install openmc_depletion_plotter

2. Install the nuclear data

pip install openmc_data
download_nndc -r b8.0
download_nndc_chain -r b8.0

3. Run the simulation scripts and produce plots

python simulate_irradiation.py

At this point the png files for each figure have been created in the figs folder

5. Produce the report in MarkDown

python produce_markdown_report.py

This takes a report template and fills in details for the version of OpenMC used, nuclear data used in MarkDown format.

6. Produce the report in PDF

To create the report in PDF this can be made by converting the MarkDown format but we need to install Latex and Pandoc.

apt-get install -y texlive-latex-base texlive-fonts-recommended
apt-get install -y pandoc
pandoc activation_handbook.md activation_handbook.pdf

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Code for automated production of a fusion materials activation handbook using OpenMC. Containing simulated activity, dose and decay heat characteristics for elements and materials exposed to neutron irradiation.

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