Looking for MCNP tutorials for a beginner

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SUMMARY

The discussion centers on resources for learning MCNP (Monte Carlo N-Particle Transport Code), particularly for beginners. Key recommendations include the new version of the MCNP Primer by J. Kenneth Shultis and Amir A. Bahadori, and the MCNP Guide by Dr. Andy Boston, which provides practical insights into simulating real events. The MCNP version 6.3 manual is also highlighted as a valuable resource, despite its length. Additionally, the CardSharp Python library is introduced as a tool for generating MCNP input decks, beneficial for newcomers to the software.

PREREQUISITES
  • Familiarity with MCNP (Monte Carlo N-Particle Transport Code)
  • Basic understanding of nuclear reactor physics
  • Knowledge of Python programming for using CardSharp
  • Access to the MCNP version 6.3 manual
NEXT STEPS
  • Study the MCNP Primer by J. Kenneth Shultis and Amir A. Bahadori
  • Read the MCNP Guide by Dr. Andy Boston for practical simulation techniques
  • Explore the CardSharp Python library for generating MCNP input decks
  • Review the MCNP version 6.3 manual for comprehensive understanding
USEFUL FOR

This discussion is beneficial for researchers, students, and professionals in nuclear engineering, particularly those new to MCNP and seeking effective learning resources and tools.

jorgenbill
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wanted to learn the MCNP for my research, but need some help, don't know nothing about that.
There some step by step tutorial in youtube or website focus on that.
Wanna make one analysis in one HTGR reactor in the case
 
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Welcome to Physics Forums @jorgenbill

There is a new version of the MCNP Primer by J Kenneth Shultis and Amir A Bahadori and there is simply no reason to start anywhere else.

Edit - Archived copy of the Primer here.

I also rate the MCNP Guide by Dr Andy Boston. Especially as that covers the simulation of 'real' events like counts on a neutron detector, which after a full reading of the manual I didn't understand until I read this guide.

If you need specific stuff the manual for 6.3 is good and public, but a long read. I would consult this before any other version of the manual even if your MCNP version is not 6.3

A few warnings. MCNP is a program written over a period of 50ish years by smart people for the use of smart people and it's going to feel crazy and confusing at the start. The methods are very clever, often not obvious and the error messages frequently don't seem to identify to the cause of the problem. Ride the wave of chaos, try to enjoy discovering how to make the program work and some of the methods it uses.

Also there are a number of people in this forum with a good grasp of the program. So if you get stuck, do ask for help.

Good luck!
 
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Is there any tutorials that might be helpful to start with?
 
Welcome to Physics Forums @Jaddyd,

I'm a little shocked that I don't seem to have a copy of the new version of the primer and with archive down neither document works.

Edit - InternetArchive is up but the front page isn't working for me. Wayback is working and I've added a link. So both documents can be viewed.
 
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I would like to bring attention to a Python library called CardSharp for generating MCNP input decks which can be especially useful for MCNP beginners: https://github.com/pnnl/CardSharpForMCNP.
It has comprehensive support for geometry and materials. There is some support for sources and tallies for detector models. Cards/features that are not yet supported can be easily inserted as raw strings. Comprehensive examples are provided.

Full disclosure: I am the developer of the library.
 
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nikhild said:
Full disclosure: I am the developer of the library.
Welcome to PF. Thanks for the disclosure, and thanks for the useful pointer. :smile:
 
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