Comments: These are ignored by Serpent.Setting up any other run parameters, here simply setting the neutron population that is to be simulated.Ĭopy and paste the input below to a file named infinite on your computer.Applying a reflective boundary condition at the geometry outer boundary to make the system infinite.Defining two geometry cells: One containing the material fuel and the other being defined as an outside cell.Defining a boundary surface for our geometry which separates our model to the inside and outside of the geometry.Defining the single material, which is called fuel in this example.The input of the model is shown below and consists of only six definitions: Testing the effect of added neutron moderation on the multiplication factor and energy spectrum of the system.
Here the infinite material is 4.0 wt-% enriched uranium with a density of 10.1 g/cm 3. The first model in this tutorial is the simplest geometry model one can imagine: an infinite homogeneous system consisting of a single material. Part 1: Infinite homogeneous system Part 1 overview Alternatively, the serpentTools python package can be used to process output files without the need for custom parsers. Python and simply use the scripts provided here as example. You can also create your own analysis scripts using, e.g. The analysis scripts may be executable also with MATLAB. OCTAVE is used for analyzing and plotting some of the results from the calculations.If this is not the case, you'll need to give the path to a cross section directory file in the input using set acelib. This tutorial assumes that you have defined a default cross section directory file for Serpent using the SERPENT_ACELIB environment variable (see the notes of set acelib). Cross section, decay data (.dec) and neutron induced fission yield (.nfy) libraries.
#INDEX NOTATION EQUILIBRIUM 3D ELASTIC STRUCTURE FULL#
If this is not the case, you'll need to replace the sss2 run-commands with the full path to your executable. you either have the executable in your PATH or have created an alias for the executable. This tutorial assumes that you can run Serpent 2 simply by typing sss2 in your terminal, i.e. This tutorial assumes that you have compiled Serpent with OpenMP parallelization and the graphics libraries. 8.2 Unresolved resonance probability table sampling.8.1 Doppler broadening rejection correction.8 Final part: Options for real life calculations.7.10.3 Generating pin power form factors.7.10.2 Generating assembly discontinuity factors.7.9 Post processing the group constant data.7.7 Running the burnup calculation for the historical variations.7.6 Adding important options for group constant generation.7.4 Setting up the historical variations.7 Part 6: Generating a set of group constants for a fuel assembly.6.6 Ideas for additional testing and tinkering in part 5.6.4.8 Plugging the extra holes in the grid plates.6.4.7 Creating 3D models for empty lattice positions.6.4.6 Setting the fuel pin lattice into the reactor.6.4 Building the Serpent model for the reactor.5.7 Ideas for additional testing and tinkering in part 4.4.6 Ideas for additional testing and tinkering in part 3.4.5 Calculating the pin power distribution.4.4.4 Calculating the k-eff for the modified system.4.4 Testing the power feedback effects in the assembly.4.3 Running the input for the assembly geometry.4 Part 3: A 2D assembly model (infinite lattice).3.7 Ideas for additional testing and tinkering in part 2.3.6 Calculating radial reaction rate distributions in the fuel pellet.3 Part 2: A 2D pin-cell (infinite lattice).2.7 Ideas for additional testing and tinkering in part 1.2.6 Testing the effect of added moderation.2.5 Calculating the flux energy spectrum.2.4 Finding the critical uranium enrichment.2.3 Running the input for the infinite system.
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