Joao Pedro
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- TL;DR Summary
- Ambient dose equivalent from a Co-60 source shielded and unshielded dose are basically the same
I was tasked with designing a shield for a Co-60 source, I decided to use ambient dose equivalent, tally 5. I got my results, followed "Radiation Problems: From Analytical to Monte-Carlo Solutions" example and arrived at a dose of X. I performed some shielding equations and arrived on a required shield of ~9.5 cm of lead to bring the dose down to 1 mSv/year, but when I went to double check my answer performing a MCNP test I am getting basically the same pSv/gamma from the tally 5 output as my unshielded input file, am I doing something wrong here? Was my initial input incorrect? (the input file is a bit disorganized since I was tinkering if it)