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Overview
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=========
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- SaltProc couples directly with the Monte Carlo neutron transport Serpent 2 and
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- enables sophisticated, multi-component online fuel reprocessing system modeling.
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- SaltProc is the first open-source tool for liquid-fueled MSR depletion
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- simulation with following capabilities:
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+ SaltProc couples directly with the Monte Carlo neutron transport code Serpent 2
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+ and enables sophisticated, multi-component online fuel reprocessing system
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+ modeling. SaltProc is the first open-source tool for liquid-fueled MSR
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+ depletion simulation with the following capabilities:
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- neutron poison removal with user-defined efficiency,
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- make-up mass loss by fresh fuel injection,
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- reactivity control by adjusting fuel feed rate or geometry change,
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- - for any reactor design,
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+ - can model any reactor design,
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- potentially, can couple with any depletion tool (i.e., MCNP, SCALE, OpenMC).
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@@ -28,33 +28,38 @@ Molten Salt Reactors. It performs three major functions:
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The code logic flow is the following:
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1. Runs Serpent (`saltproc.depcode.run_depcode() `)
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- 2. Parses through the output `*_dep.m ` file and create PyNE Material object for each burnable material.
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+ 2. Parses through the output `*_dep.m ` file and creates PyNE Material object
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+ for each burnable material.
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3. Processes Fuel (`saltproc.app.reprocessing() ` and `saltproc.refill `):
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- * Passes fuel composition throughout Processes objects (reprocessing system components) to remove poisons with specific efficiency.
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- * Add back fissile and/or fertile material to make-up loss of material.
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+ * Passes fuel composition throughout Processes objects (reprocessing system
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+ components) to remove poisons with specific efficiency.
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+ * Adds back fissile and/or fertile material to make-up loss of material.
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4. Records data:
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- Depleted fuel composition (`materials/fuel/before_reproc ` table in HDF5)
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- - Reprocessed fuel composition (`materials/fuel/after_reproc ` table in HDF5)
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- - Multiplication factor at the beginning and at the end of depletion step (`simulation_parameters/keff_bds `, `simulation_parameters/keff_eds `)
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- - Effective Delayed Neutron Fraction (:math: `\beta _{eff}`) at the end of the depletion step (`simulation_parameters/beta_eff_eds `)
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+ - Reprocessed fuel composition (`materials/fuel/after_reproc ` table in
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+ HDF5)
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+ - Multiplication factor at the beginning and at the end of depletion step
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+ (`simulation_parameters/keff_bds `, `simulation_parameters/keff_eds `)
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+ - Effective Delayed Neutron Fraction (:math: `\beta _{eff}`) at the end of
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+ the depletion step (`simulation_parameters/beta_eff_eds `)
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- Waste and feed streams from each `Process ` (`materials/in_out_streams/ `)
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- 5. Repeat 1-4.
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+ 5. Repeats 1-4.
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The Future
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-----------
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- Number of features will be implemented in SaltProc soon. Support of various
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+ A number of features will be implemented in SaltProc soon. Support of various
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depletion codes (e.g., OpenMC) will be added.
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.. warning ::
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SaltProc is a relatively new project and is still under heavy development.
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- Although we will make a best effort to maintain compatibility with the
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+ Although we will make our best effort to maintain compatibility with the
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current API, inevitably the API will change in future versions as SaltProc
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matures.
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