Recent content by skoch
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MCNP6 gamma dose tally problems
First off, I want to thank you for how quickly you are responding to my thread. I'll quote your response with my reasonings below: While I was running a significantly shorter version of this problem (2000 nps) to check my inputs, I was printing all of the tables for my output file. One of the...- skoch
- Post #5
- Forum: Nuclear Engineering
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MCNP6 gamma dose tally problems
That is incredibly helpful, thank you. I have a few other questions to help me understand my input a little better: Does the activity of the source cell as calculated by MCNP affect the tally? Am I correct in using PAR=SD in my SDEF to include the gammas from Yb-177's daughter Lu-177? Is using...- skoch
- Post #3
- Forum: Nuclear Engineering
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MCNP6 gamma dose tally problems
Hello, I am a very new MCNP user and have been doing my best to learn on my own. I am struggling to get this problem I am working on to be even somewhat correct. I am trying to determine the dose rate for a person outside a lead-lined room(box) with a 20 TBq Yb-177 source inside. I'm using an...- skoch
- Thread
- Mcnp6
- Replies: 5
- Forum: Nuclear Engineering