Hello
1 when I run depletion,there is a warning about probability.I use the ‘chain_casl_sfr.xml’.Does it significantly affect burnup results?
2 In addition,I model the cermet fuel include lots of 100 micron UO2 fuel pellets,it cause that i can’t get precise volume but with a error when I run Random volume calculation,because the geometry become complex.Does it also significantly affect burnup results?
(UO2 is in red)
3 Besides,It is hard for me to use ‘diff_burnable_mats’ of operator class in this geometry,so can i set several material with the same component,then i give them for different assembly to differentiate materials that reappear in multiple places.
Thank you very much!Good luck to all.
It’s important for OpenMC to know the correct volume of burnable materials for a depletion problem. If the volume is wrong, your results will be wrong too. Using a stochastic volume calculation seems like a good approach for this – what error are you seeing when you try running the stochastic volume calculation?
in about 100 days,there seems a upcurve,my fuel is 94 wt% 235U for fast spectrum reactor.
I use all nuclides in ‘chain_casl_sfr.xml’.I can’t understand why there is peak in 100 days,there is only 6wt% 238U which can be used for breeding.
