# Create a source based on a material decay of a cell **URL:** \ **Category:** User Support\ **Created:** [August 12, 2022, 1:58pm UTC](https://openmc.discourse.group/t/create-a-source-based-on-a-material-decay-of-a-cell/2223 "2022-08-12T13:58:34Z")\ **Posts on this page:** 2\ **Page:** 1
**Author:** ![zprieto](https://avatars.discourse-cdn.com/v4/letter/z/7bcc69/32.png) [@zprieto](https://openmc.discourse.group/u/zprieto)\ **Post date:** [August 12, 2022, 1:58pm UTC](https://openmc.discourse.group/t/create-a-source-based-on-a-material-decay-of-a-cell/2223/1 "2022-08-12T13:58:34Z")
Hi, I want to know if it is possible to create a source based on a material decay of a cell. In the case it is, how can I implement it in the settings source? I was thinking about defining the material and the geometry. And after that run a fixed source simulation with the source defined in a cell from the geometry and with its composition which is a radioactive material. I want to calculate the dose in another cell produced by that material decay. ---
**Author:** ![paulromano](https://yyz2.discourse-cdn.com/free1/user_avatar/openmc.discourse.group/paulromano/32/486_2.png) [@paulromano](https://openmc.discourse.group/u/paulromano)\ **Post date:** [August 15, 2022, 3:18pm UTC](https://openmc.discourse.group/t/create-a-source-based-on-a-material-decay-of-a-cell/2223/2 "2022-08-15T15:18:22Z")
Hi @zprieto and welcome to the community! Our development team is actively working on a capability for defining sources based on material decay as part of an ongoing [fusion-energy related project](https://github.com/orgs/openmc-dev/projects/1). Some of the first pieces for that have been merged in our main branch, namely the ability to get a decay photon energy distribution for a given nuclide, and we’ll be slowing building on top of that to hopefully make the workflow for doing these calculations pretty seamless. Stay posted — within a few months this should start to take shape more!