Search found 79 matches

by Ana Jambrina
Thu Sep 17, 2020 4:10 pm
Forum: Users
Topic: ECCO-1968 Neutron Energy Group Structure
Replies: 9
Views: 54

Re: ECCO-1968 Neutron Energy Group Structure

I'm a little bit confuse here, what is exactly the problem? As Antti said, ECCO 1968-group structure goes up to ~20 MeV, which is consistent with Serpent Wiki: 1.9640330000E+01 MeV = 19.64033 MeV ~ 20 MeV.
by Ana Jambrina
Thu Sep 17, 2020 3:19 pm
Forum: Users
Topic: ECCO-1968 Neutron Energy Group Structure
Replies: 9
Views: 54

Re: ECCO-1968 Neutron Energy Group Structure

Standard group structures data, i.e. ECCO-2000, can be requested through RSICC or NEA Data Bank.
by Ana Jambrina
Thu Sep 17, 2020 1:55 pm
Forum: Users
Topic: ECCO-1968 Neutron Energy Group Structure
Replies: 9
Views: 54

Re: ECCO-1968 Neutron Energy Group Structure

ECCO-2000 is a 1968-group neutron structure containing a subset of both the VITAMIN-J and XMAS energy group boundaries. It is aimed at fine group reactor cell calculations for fast, intermediate and thermal reactor applications. The basic lethargy grid is 1/120 with a few exceptions from 20 MeV to 5...
by Ana Jambrina
Thu Sep 17, 2020 9:04 am
Forum: Users
Topic: NormalizeCompositions: max afrac problem
Replies: 3
Views: 72

Re: NormalizeCompositions: max afrac problem

Volumes can be defined either manually or by using the Monte Carlo volume-checker routine ('mcvol' card, http://serpent.vtt.fi/mediawiki/index.php/Input_syntax_manual#set_mcvol ; or 'checkvolumes' command line option, http://serpent.vtt.fi/mediawiki/index.php/Installing_and_running_Serpent#Monte_Car...
by Ana Jambrina
Wed Sep 16, 2020 2:35 pm
Forum: Users
Topic: NormalizeCompositions: max afrac problem
Replies: 3
Views: 72

Re: NormalizeCompositions: max afrac problem

The failure comes from a check of the (maximum) atomic fraction: which is completely off. Have you checked the associated volume? Inconsistent volumes would result in incorrect nuclide compositions.
by Ana Jambrina
Sun Sep 06, 2020 1:05 pm
Forum: General
Topic: Reaction rate vs Burnup.
Replies: 8
Views: 259

Re: Reaction rate vs Burnup.

The ENDF reaction MT numbers are universal and related to isotopic cross sections. These reactions may not be used with materials consisting of more than one nuclide. The result is multiplied by the material atomic density and microscopic reaction rates can be calculated by setting the density to un...
by Ana Jambrina
Thu Sep 03, 2020 6:04 pm
Forum: Users
Topic: Print 1-group XS with xsplot
Replies: 4
Views: 102

Re: Print 1-group XS with xsplot

Maybe you can try by modifying: readinput.c routine line (12397-12400, Serpent 2.1.31 version) corresponding to the resolution of the plot (number of points): if (k < np) WDB[DATA_XSPLOT_NE] = TestParam(pname, fname, line, params[k++], PTYPE_INT, 10, 10000); with the a more suitable interval for you...
by Ana Jambrina
Thu Aug 27, 2020 2:10 pm
Forum: Users
Topic: Corner Point Indexing in the ADF option
Replies: 3
Views: 142

Re: Corner Point Indexing in the ADF option

Could you post the input you are using for testing?
by Ana Jambrina
Tue Aug 25, 2020 9:48 am
Forum: Users
Topic: HTTR Whole Core Sample Input
Replies: 4
Views: 827

Re: HTTR Whole Core Sample Input

There are some HTGR examples available (particle cell, fuel-pebble and fuel compact), that might help you with the model.
(See: http://serpent.vtt.fi/mediawiki/index.p ... _examples)
by Ana Jambrina
Tue Aug 25, 2020 9:45 am
Forum: Users
Topic: calculations with reduced delayed neutrons
Replies: 2
Views: 73

Re: calculations with reduced delayed neutrons

To relate the mass flow structure with the precursors you might want to try modifying the precursors positions (precursors source distribution) in the '.precpoints' file. That would simulate the material/precursor movement/transferral ('mflow'). However, that also would require to split the calculat...