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Select the moderating material used for neutron scattering and thermalization in the simulation.
The moderator determines the average energy loss per collision, the thermalization rate, angular scattering behavior, ...
Select the geometry that is used in the simulation.
The geometry determines if a neutron escapes or is absorbed/thermalizes in the chosen material. It can also be plotted. Each geometry has it's specific parameters that are displayed after selecting a geometry type.
Select the settings that are used in the simulation.
The settings determine where the neutron source is positioned, the starting energy of the neutrons, the number of neutrons used in the simulation and the seed number for the simulation. This number provides the repeatability of the simulation. The thermal energy slider is used for the whole simulation, change it after running the simulation and then plot the available graphs. You can find it in the toggleable sidebar on the left side.
Create and name a setup with the chosen parameters for the simulation.
First give your setup a unique name and click Create XML Configuration. If that name is already in use the website will give you a choice of overwriting the existing setup or creating a new version of it. The website adds a suffix to the name, describing the number of neutrons, moderating material and the geometry shape used in the simulation.
Run the simulation for the selected setup.
Select a setup you created and run the OpenMC simulation. If the setup is already run you will see an annotation text ✅ besides the setup name in the Select setup dropdown. You do not need to resimulate already run setups, but it is possible to do so. If a setup is already run you can select it and plot a graph without resimulating the setup.
View cross sections for the material used in the selected setup.
Displays cross sections for the material of the currently selected setup. For custom materials the data is read directly from the generated HDF5 file. For standard materials the data is read from the OpenMC cross section library.
Visualize neutron moderation tracks. Visualizing one particle gives a color coded energy loss graph. You can also visualize the used geometry.
After selecting a setup plot the particle tracks. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. If you want to visualize the geometry tick the box Show Geometry. Remember you can also change the thermalisation energy with the sidebar on the left. Plotting more than 100 particles at once may be slow and plotting more than 1000 is not advised.
Visualize neutron energy loss per collision.
After selecting a setup plot the energy loss per sollision graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100.
Plot an up/downscatter heatmap for particle energy loss vs. initial energy before collision.
After selecting a setup plot the up/downscatter heatmap. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There are also several plotting options: ΔE log scale, Collision counts log scale and Normalize by source energy. You can also select a energgy loss ΔE range. Note that if ΔE log scale is selected the range must be positive (0 is not included).
Plot a probability of scattering histogram from the initial energy bin E to all possible enrgies.
After selecting a setup plot the scattering histogram. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There is also an option to select the initial energy bin E (in eV) from which the scattering occurs and the bin number used in the historgam. The histogram also shows the theoretical probability of scattering form E to E', where
Plot collisions until thermal histogram graph. The simulated distribution is compared to a Poisson distribution.
After selecting a setup, plot the collisions-until-thermalisation histogram. An option to select the desired particles is given through particle indices. For example, the input 1 shows the first particle, 1–10 shows the first 10 particles, and 1–100–10 shows each 10th particle from 1 to 100.
The simulated distribution of collisions until thermalisation is compared to a Poisson distribution
where the mean number of collisions is
Here
where
Plot Mean free path vs. initial energy. The MFP for particles are shaded in the background while the average MFP is at the front in red.
After selecting a setup plot MFP vs. initial energy graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100.
Plot the cosine of the scattering angle distribution or only the scattering angle distribution.
After selecting a setup and plot type, plot the graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1–10 shows the first 10 particles, and 1–100–10 shows each 10th particle from 1 to 100.
The average cosine of the scattering angle is defined as
For elastic scattering on a nucleus of mass number
For moderator molecules with more than one atom, we compute the average as
It needs to be noted that the angle theoretical value is just an approximation, because there is no easily interpretable equation to describe it
Plot a scattering heatmap for the cosine of the angle vs. initial energy before collision.
After selecting a setup plot the angle vs. energy heatmap. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There is also a plotting option for the logarithmic scale of counts for better visibility.
Plot a
After selecting a setup plot and the graph type plot the
Plot analytic vs. simulated
After selecting a setup and the plot type you can plot the graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There are also several plotting options: Upscattering allowed and number of bins.
The theoretical
where
Plot the
After selecting a setup you can plot the graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There are also several plotting options: Log y scale, Log x scale, Theory, E normalized and Include upscattering.
The relative energy loss per collision is defined as
For elastic scattering on a nucleus of mass number
Assuming isotropic scattering in the center-of-mass frame, the average relative energy loss per collision is
If E normalized is selected
Plot the
After selecting a setup and the plot type you can plot the graph. An option to select the desired particles is given through particle indices. Input your particle indices in the way shown in the example. For example, the input 1 shows the first particle, 1-10 shows the first 10 particles, 1-100-10 shows each 10th particle from 1 to 100. There are also several plotting options: Log y scale, Log x scale, Theory, E normalized and Include upscattering.
The relative energy loss per collision is defined as
For elastic scattering on a nucleus of mass number
Assuming isotropic scattering in the center-of-mass frame, the average relative energy loss per collision is
If E normalized is selected