Where Are the Other Detectors for F5 Tally in MCNP?

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Discussion Overview

The discussion revolves around the functionality of multiple detectors for a single F5 tally in the MCNP code, exploring the output behavior and user experience. Participants examine the implications of using multiple detectors versus separate tally numbers, and the limitations of the MCNP manual regarding this feature.

Discussion Character

  • Technical explanation
  • Debate/contested

Main Points Raised

  • Will questions why only the first F5 detector result appears in the output file, despite the ability to define multiple detectors.
  • Some participants suggest that using separate tally numbers (f15, f25, f35) should yield distinct results, while others speculate that multiple points on the same tally may sum to a single answer.
  • Alex clarifies that the option to use F15 with multiple detector locations should theoretically provide results as if each detector had a separate tally number.
  • One participant notes that the MCNP manuals provide limited guidance on this feature, particularly in the latest version (MCNP 6.3), and mentions that additional results may be found in the .m file with minimal labeling.
  • A participant with less experience in MCNP6 discusses the definitions of tally, bin, and detector, and explains the evolution of tally capabilities from MCNP5 to later versions.
  • It is noted that unless the 'ND' keyword is used, results for each detector should be visible according to the manual, although there is uncertainty about the behavior of earlier manuals.
  • There is a light-hearted comment about the user-friendliness of the code, comparing it to luxury vehicles.

Areas of Agreement / Disagreement

Participants express differing views on the output behavior of multiple detectors in MCNP, with some believing that results should be visible for each detector while others remain uncertain about the implementation and user experience. No consensus is reached regarding the functionality and clarity of the MCNP manuals.

Contextual Notes

Participants highlight limitations in the MCNP manuals, including a lack of clarity and user-friendly guidance, as well as potential discrepancies between different versions of the manuals and the actual code behavior.

Will_007
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TL;DR
where is the output for multiple F5 tally detectors
The MCNP manual states that you can have multiple detectors for a single F5 tally. Say you have f15:n x1 y1 z1 r x2 y2 z2 r.....Thing is, my output file only lists the tally result for the first f5 detector (x1,y1,z1). Where are other detectors for this tally? Is there a reason code developers enabled this method of defining multiple detectors vs just using f15, f25, f35....for each one?

Thanks,
Will
 
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f15, f25, f35 should all work and give separate answers, I wonder if you specify multiple rings or points on the same tally if it sums all the calculations to a single answer. I might do a test. I'd say the code is not 'clever' but internally it's extremely clever. What it's not is user friendly. It's derived from an old code and it's still in FORTRAN, which has limited string handling capabilities, everything has to be quite explicit; syntax is fairly brittle and error checking is woefully lacking.
 
Hey Alex - so yes, F15, F25....can be used separately but this option allows you to use F15 and then list multiple detector locations (not ring or a sum...the results appear to be as if you separately assigned a tally number to each). Discussion in the manual is limited, but in latest manual online (MCNP 6.3), this is the statement below. It looks like only the first detector belonging to the tally is in the output file, the rest are in the .m file but minimal labels (not user friendly at all)
1675206546484.png
 
I have almost no experience with MCNP6, so I've done some reading. There also isn't much in the way of a glossary. I understand a tally is an F card, a bin is when it's split into multiple results by energy, position or time and a detector is an object that has to be inserted in addition to the existing geometry and cell cards.

F1,2,3,4,6 and 7 don't involve detectors, they use an existing object. MCNP5 and later allows many objects on the same tally and how the results are shown depends upon parentheses.

MCNP5 only allows one ring or point per tally but the same note is in the MCNP5 manual, just meaning F5 can do point arrays (and maybe other reasons) so don't expect to do 20 (the detector limit for that version) F5 tallies under all circumstances.

X 2.6.0, 6.2 and 6.3 manuals allow multiple ring and point detectors per tally and the expected behavior is that is write a tally total as well as individual results for each detector unless this is suppressed with the 'ND' keyword.

The 6.1 and 6.1.1 manuals are maybe unhelpful, and they appear to be derived from the MCNP5 manual, so the behavior might not match the code.

So yeah, unless you are using the 'ND' keyword you should see a result for every detector on the line according to the manual. I also have no idea what the .m file is. :)
 
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thanks - .m file is the MCTAL file (obviously! :) )...one day when LANL makes this a user-friendly code it will transform it from formula one to bentley
 
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