Number of nuclides in depletion calculation

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Yousef1986
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Number of nuclides in depletion calculation

Post by Yousef1986 » Tue Sep 19, 2017 10:01 am

Dear all,

Is there a way to know how many nuclides (i.e. fission products, actinides, fission yield and decay data) are included in depletion calculation when using endfb7.xsdata, endfb7.dec, and endfb7.nfy?

P.S.: By the way, I am using Serpent 2.1.29
Yousef Alzaben
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Karlsruhe Institute of Technology (KIT)

Ville Valtavirta
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Re: Number of nuclides in depletion calculation

Post by Ville Valtavirta » Tue Sep 19, 2017 3:19 pm

Hi Yousef,

the nuclide data used in the calculation should be summarized in the beginning of the file <input>.out produced during the pre-processing of the calculation so you should be able to tell afterwards at least.

-Ville

Yousef1986
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Re: Number of nuclides in depletion calculation

Post by Yousef1986 » Tue Sep 19, 2017 3:38 pm

Thanks Ville for your reply.

I can see now that I have 1359 nuclides included in the calculation of which 306 Transport nuclides and 1053 Decay nuclides.

I believe that only the transport nuclides have XS data available. What about FP nuclides? Are they included in the 306 Transport nuclides?
Yousef Alzaben
Ph.D. Student
Karlsruhe Institute of Technology (KIT)

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Jaakko Leppänen
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Re: Number of nuclides in depletion calculation

Post by Jaakko Leppänen » Tue Sep 19, 2017 7:42 pm

Transport nuclides include both actinides and fission products. The 5th column in the table at the beginning of the <input>.out file has either "TRA" or "DEC", indicating whether the nuclide has transport cross sections or only decay data.
- Jaakko

Yousef1986
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Re: Number of nuclides in depletion calculation

Post by Yousef1986 » Wed Sep 20, 2017 10:00 am

Thanks Jaakko for the clarification
Yousef Alzaben
Ph.D. Student
Karlsruhe Institute of Technology (KIT)

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