From 194a20b7d5cbc688d52981a8cb5e045e8f2d93e0 Mon Sep 17 00:00:00 2001 From: Kenneth Assogba Date: Fri, 15 Nov 2024 23:42:18 +0100 Subject: [PATCH] Clean doc --- src/README.md | 61 ++++++++++++++++++++++++++++++++++++++++++--------- 1 file changed, 51 insertions(+), 10 deletions(-) diff --git a/src/README.md b/src/README.md index e5bd935..9222e3d 100644 --- a/src/README.md +++ b/src/README.md @@ -1,15 +1,56 @@ # Source general 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. + ## Directory structure -src/ -├── core/ -│ ├── foo.h -│ ├── foo.cpp -│ ├── foo.test.cpp -│ ├── bar.h -│ ├── bar.cpp -│ └── bar.test.cpp +demeter/ +├── src/ +│ ├── model/ +│ │ ├── cell.hpp +│ │ ├── cell.cpp +│ │ ├── pincell.hpp +│ │ ├── pincell.cpp +│ │ ├── material.hpp +│ │ └── material.cpp +│ └── solve/ +│ ├── solver.hpp +│ └── solver.cpp └── tests/ - ├── functional_test1/ - └── integration_test1/ + ├── unit/ + ├── benchmark/ + └── regress/ + +## 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 + - Mesh + - Symetry + - 1/2 + - 1/8 + - Boundary counditions + - Vaccum + - Reflexion + +## Usage example + +Na + +## Solvers + +Na