Dear experts, I have determined two different volumes of fuel in the openmc input file, let’s say both of them contain U235 nuclide. How can I observe the total atomic density change for these?
As far as I know, openmc does not do this process. You can handle the total calculation with the help of post processing. Or through a formula. These experts can help you with this issue. @gridley@Daedalus@Shimwell
Here, the change in total atomic density in depletion of any nuclide for materials with two different IDs is desired.He wants to find the total thorium depletion in material id 1 and 6 to show them both in a single graph.For example, they stated this as TOT_ADENS in Serpent.
Yes, it saves the material with two different IDs to the h5 file. For example, 78 pin 1 id, 234 pin 3 id. But here we want to find the total change in these. That is, the total Th232 depletion in the number of pins 78 + 234. Do we need to produce a different formula to calculate this?
I guess if you have the change for the two individual pins you can combine those two results to get the total. Perhaps I’ve misunderstood something here. But would you not just add them up?
Yes, I think it is a logical solution to add them together to find the change in Th232 atomic density on pins with two different IDs.I will combine the list of atomic density changes at id 1 and id 6 with the addition process.