# Fetching Depletion Results

**URL:** <https://openmc.discourse.group/t/fetching-depletion-results/4103>\
**Category:** User Support\
**Created:** [March 29, 2024, 6:02pm UTC](https://openmc.discourse.group/t/fetching-depletion-results/4103 "2024-03-29T18:02:47Z")\
**Posts on this page:** 2\
**Page:** 1

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**Author:** ![msood](https://avatars.discourse-cdn.com/v4/letter/m/e274bd/32.png) [@msood](https://openmc.discourse.group/u/msood)\
**Post date:** [March 29, 2024, 6:02pm UTC](https://openmc.discourse.group/t/fetching-depletion-results/4103/1 "2024-03-29T18:02:47Z")

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Is there a way to retrieve depleted data at a specific burnup step and generate a new materials.xml file with the appropriate units?

I came across a suggestion in another post which involved using the following code:  
results = openmc.deplete.Results(‘depletion\_results.h5’)  
materials\_dep = results.export\_to\_materials(burnupstep) # ‘burnupstep’ is an integer value

However, upon inspecting the new materials.xml file, I noticed that the nuclides didn’t have the correct units, despite the xml file indicating that the values were in ‘ao’. What are the units in this file and is there a way to just export them in ‘ao’ at a particular burnup step?

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**Author:** ![wahidluthfi](https://yyz2.discourse-cdn.com/free1/user_avatar/openmc.discourse.group/wahidluthfi/32/3375_2.png) [@wahidluthfi](https://openmc.discourse.group/u/wahidluthfi)\
**Post date:** [June 2, 2024, 3:14pm UTC](https://openmc.discourse.group/t/fetching-depletion-results/4103/2 "2024-06-02T15:14:05Z")

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Hello MSood,  
I think the nuclide compositions generated from depletion results has a units of atoms/barn-cm, you could double check it with the value provided at the BOC since you usually know your composition at the BOC.