Hi OpenMC community,
I’m very new to this software, but I am currently writing a project in which I am supposed to simulate a Molten Salt Reactor. The main goal of the project is to simulate the reactor and examining the build-up of Xe-135. To do this I have written a depletion code which, in theory, should simulate each individual time-step, extract the amount of Xenon and fuel, and resume the simulation with the given amounts.
I start by writing a function which defines my materials, but later on in a different function I wish to use these materials, but the code doesn’t recognize the local variables. So is there any way to “re-assign” the different materials from a global scope to local variables within the function?
Please excuse me if I am doing any formatting wrong in this post, I am quite new to this.
Any help is greatly appreciated!
(I have attached the “single-time-step-run” piece of code as a .png, materials is defined elsewhere in the code)