Cross section data

This category replaces the missing input manual
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Sincler
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Cross section data

Post by Sincler » Tue Mar 08, 2016 9:21 pm

I wanted to use the same cross section data for the same isotope in diferent codes, but I had a problem to use the ENDF libraries from MCNP in Serpent. When I try burn, it appears the following message to one isotope: "ENDF law 67 not supported".

How I can solve this?

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Jaakko Leppänen
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Re: Cross section data

Post by Jaakko Leppänen » Tue Mar 08, 2016 11:57 pm

This law is rarely used, so it has not yet been in implemented in Serpent. The only workaround is to remove the nuclide from the directory file or use another library altogether.
- Jaakko

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Sincler
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Re: Cross section data

Post by Sincler » Wed Mar 09, 2016 10:31 pm

The last problem is solved, but when I run (in 2.1.25) other message shows:
_______________________________________________________
Setting nuclide compositions for burnable materials...

***** Tue Mar 8 18:15:26 2016:

- MPI task = 0
- OpenMP thread = 0
- RNG parent seed = 1457471664

Fatal error in function BurnMatCompositions:

No S(a,b) flags?

Simulation aborted.

_______________________________________________________

Any suggestion?

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Jaakko Leppänen
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Re: Cross section data

Post by Jaakko Leppänen » Thu Mar 10, 2016 11:13 am

See: this related post

What kind of geometry do you have? Do you think it would be simple enough for debugging?
- Jaakko

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Sincler
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Re: Cross section data

Post by Sincler » Thu Mar 10, 2016 5:34 pm

I have a complete TRIGA Mark I.
I tried run a simple geometry with just the active zone of fuel, in this case I don't have problem.
The simulation run without problem too when I use the original package of cross sections.

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Jaakko Leppänen
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Re: Cross section data

Post by Jaakko Leppänen » Thu Mar 10, 2016 8:22 pm

OK. I think this is a problem that emerges from some very specific combination of input options. I'd like to get this fixed for the next update. Could you send me your input file (the one that fails) for testing?
- Jaakko

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Re: Cross section data

Post by satkinson » Thu Mar 24, 2016 1:38 pm

Hi Jaakko,

Was this resolved? I have changed the source code to warn instead of Die but the simulation is still aborted with this error message. Let me know if you want my input to help resolve this.

Cheers,

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Re: Cross section data

Post by Jaakko Leppänen » Fri Mar 25, 2016 12:17 am

No, we haven't solved it yet. Do you have a test case that could be used debugging? I don't have any input at the moment that produces this error.
- Jaakko

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Re: Cross section data

Post by satkinson » Sat Mar 26, 2016 8:11 pm

Absolutely have no idea what I did but it works now. If you include usym you have to place the usym line after the interface card. All I can see that I changed was usym to universe zero and then removed the extra set sym line I had in there by mistake.

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Jaakko Leppänen
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Re: Cross section data

Post by Jaakko Leppänen » Sun Mar 27, 2016 1:01 am

That doesn't make any sense, which is a strong indication that it's some sort of memory issue. So the error reappears if you change the order of usym and ifc?

Have you tried running the calculation in debug mode? (-DDEBUG option enabled in the Makefile)
- Jaakko

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