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Reorganisation and docs
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kennethassogba committed Nov 15, 2024
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7 changes: 5 additions & 2 deletions README.md
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Demeter<sup>1</sup> is a modern and open source deterministic neutron transport code for reactor simulations. The code is designed to perform 3D fixe source and eigenvalue calculations by solving the multi-group neutron transport equation.

Numerically, the physics part is coded in C++ with Python as a user interface for easy and fast utilisations. Cmake is used to build configurations.
The physics is coded in C++ with Python as user interface for easy and fast usage.

<sub>1. DEterMinistic nEutron Transport solvER</sub>

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- [x] Add AddressSanitizer, ThreadSanitizer, MemorySanitizer.
- [x] Setup Github Action.
- [x] Improve Github Action, by fixing OpenMP not found and with recent version of compiler and Eigen.
- [x] Choose a code style (Google style eg) and setup a linter.
- [x] Setup clang-format with Google style.
- [ ] Setup clang-tidy.
- [ ] Fix how to launch clang-tidy locally and on action.
- [ ] Setup gcc analizer.
- [ ] Code Goemetry.
- [ ] Code mesh.
- [ ] Setup directory structure => vector-of-bool/pitchfork.
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# Spec

A good way to get early adopters might be to be a drop-in replacement for OpenMOC or OpenMC.
But we choose to design a simplified interface.

## Material and Cross section

- Material : describe a material with its cross-sections
- vec sigma_t total or transport cross-section
- vec sigma_a absorption cross-section
- mat sigma_s scattering cross-section
- vec sigma_f fission cross-section
- vec nu_sigma_f nu*fission
- vec chi
- bool fissible
- str name (optional)

## Geometry

Cell
PinCell : cell with concentric annular regions
Lattice : set or PinCell or set of Lattice

Symetry 1/2 1/8
Boundary coundition : Vaccum Reflexion

## Usage example

Na

## Solvers

Na

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