Output data from SERPENT 2.1.24

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Sasha
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Output data from SERPENT 2.1.24

Post by Sasha » Thu Oct 15, 2015 6:50 pm

Hello,

Sorry, I have a question regarding the output data from SERPENT 2.1.24.
I've used SERPENT 1.1.19 for the generation of cross-section data. These data are used as an input for a reactor physics code, and certain variables must be always provided to this code. I would like to use SERPENT 2.1.24 for the same purpose, but I could not find some of the variables, which are provided in the output from SERPENT 1.1.19.
These variables are the following:
- Number of decay heat precursor groups: DH_N_PREC
- Precursor group-wise decay constants: DECAY_CONSTANT
- Decay heat group-wise decay constants: DH_PREC_LAMBDA
- Transport cross-section: TRANSPXS
- Absorption cross-section: ABSXS
- Fission neutron production cross section (Nu-fission): NSF
- Average fission heating value (in MeV): FISSE
- Fission cross section: FISSXS
- Total scattering production cross section: SCATTPRODXS
- Surface discontinuity factors: ADFS
- Decay heat group-wise heat constants: DH_PREC_LAMBDA

Did I miss them in the output file or they have different names in the current version?

Thank you very much in advance for your time and response!
With best regards,
Sasha.

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Jaakko Leppänen
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Re: Output data from SERPENT 2.1.24

Post by Jaakko Leppänen » Fri Oct 16, 2015 4:29 pm

Precursor group-wise decay heat data has not yet been implemented in Serpent 2. Transport, absorption, fission, fission neutron production and fission energy production cross sections calculated in infinite spectrum are in INF_TRANSPXS, INF_ABS, INF_FISS, INF_NSF and INF_FISSE. The corresponding critical spectrum cross sections are found in similar variables starting with B1_. Scattering production cross sections are in INF_SCATTP0.

ADF calculation requires an additional input card, described in: http://ttuki.vtt.fi/serpent/viewtopic.php?f=24&t=1875

Note that unlike in Serpent 2, the total values are not printed, so the first value in the vector corresponds to the highest energy group.
- Jaakko

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Re: Output data from SERPENT 2.1.24

Post by Sasha » Tue Oct 20, 2015 6:02 pm

Hi Jaakko,

Thank you very much for the clarification!

With best regards,
Sasha.

s.pfeiffer
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Re: Output data from SERPENT 2.1.24

Post by s.pfeiffer » Tue Mar 27, 2018 8:55 pm

Hi Jaako,

Have any of these variables been introduced in Serpent 2.1.30 maybe with a different name?

- Number of decay heat precursor groups DH_N_PREC
- Precursor group-wise decay constants: DECAY_CONSTANT
- Decay heat group-wise decay constants: DH_PREC_LAMBDA
- Number of delayed neutron precursor groups: PRECURSOR_GROUPS
- Physical delayed neutron fraction: BETA_ZERO

Thank you very much in advance for your time and response!
With best regards,
Sharon

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Jaakko Leppänen
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Re: Output data from SERPENT 2.1.24

Post by Jaakko Leppänen » Wed Mar 28, 2018 1:14 pm

The physical delayed neutron fractions are given in RES_FWD_ANA_BETA_ZERO. The number of precursor groups is not printed, but I'll add it in the next update.
- Jaakko

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Re: Output data from SERPENT 2.1.24

Post by Carlos Juárez » Fri Apr 10, 2020 2:56 am

Hello,

I have been using Serpent 2.1.27 and I would like to know how the decay constant for precursors has been named in the res file?

Thank you,
Carlos

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Jaakko Leppänen
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Re: Output data from SERPENT 2.1.24

Post by Jaakko Leppänen » Fri Apr 10, 2020 11:21 am

Serpent calculates delayed neutron parameters using different methods. The precursor decay constants are named "*_LAMBDA", for example:

Code: Select all

ADJ_IFP_IMP_LAMBDA        (idx, [1:  18]) = [  5.42675E-01 0.01029  1.24667E-02 0.0E+00  2.82917E-02 6.0E-09  4.25244E-02 7.9E-09  1.33042E-01 5.5E-09  2.92467E-01 6.1E-09  6.66488E-01 0.0E+00  1.63478E+00 5.4E-09  3.55460E+00 0.0E+00 ];
There are 9 value - relative error pairs. The first one is for the total and the remaining 8 for the precursor groups (this is with JEFF data, ENDF uses 6 groups).
- Jaakko

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Re: Output data from SERPENT 2.1.24

Post by Carlos Juárez » Sat Apr 11, 2020 12:52 am

Thank you Jaakko.

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