# Openmc for shielding calcs

**URL:** <https://openmc.discourse.group/t/openmc-for-shielding-calcs/3932>\
**Category:** User Support\
**Created:** [February 19, 2024, 10:34pm UTC](https://openmc.discourse.group/t/openmc-for-shielding-calcs/3932 "2024-02-19T22:34:15Z")\
**Posts on this page:** 2\
**Page:** 1

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**Author:** ![cclaro](https://avatars.discourse-cdn.com/v4/letter/c/9de053/32.png) [@cclaro](https://openmc.discourse.group/u/cclaro)\
**Post date:** [February 19, 2024, 10:34pm UTC](https://openmc.discourse.group/t/openmc-for-shielding-calcs/3932/1 "2024-02-19T22:34:15Z")

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Hello! I would like to calculate dose rates on the surface as well as at a few specified distances from a cylindrical reactor shield. I would like to know the gamma and neutron specific doses as well, how can i begin attacking a problem like this as i am new to this program as well as particle transport programs as a whole.

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**Author:** ![Shimwell](https://yyz2.discourse-cdn.com/free1/user_avatar/openmc.discourse.group/shimwell/32/3876_2.png) [@Shimwell](https://openmc.discourse.group/u/Shimwell)\
**Post date:** [February 20, 2024, 11:25am UTC](https://openmc.discourse.group/t/openmc-for-shielding-calcs/3932/2 "2024-02-20T11:25:10Z")

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I have a few examples that might be handy

This folder has tasks that cover **surface** and **cell**  **dose** from **gamma** and **neutrons**

> <https://github.com/fusion-energy/neutronics-workshop/tree/main/tasks/task_09_CSG_instantaneous_dose_tallies>
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> //github.com/fusion-energy/neutronics-workshop/tree/main/tasks/task\_09\_CSG\_instantaneous\_dose\_tallies

best of luck