Search found 561 matches

by Ana Jambrina
Mon Aug 17, 2020 8:03 pm
Forum: Bugs, problems, questions & feeback
Topic: S(a,b) ENDF/BVII.1
Replies: 7
Views: 6195

Re: S(a,b) ENDF/BVII.1

ENDF/B-VIII.0 follows, as its predecessor, a continuous S(a,b) format - not supported in Serpent 2.1.31. ENDF/B-VIII.0. has seen an extended upgrade (including, light nuclei, structural materials, actinides, fission energy release, prompt fission neutron and γ-ray spectra, thermal neutron scattering...
by Ana Jambrina
Sun Aug 16, 2020 11:52 pm
Forum: Users
Topic: Source rate normalization
Replies: 1
Views: 504

Re: Source rate normalization

Normalisation to source rate, ‘srcrate’, for external source calculation: the total source rate refers to the rate at which neutrons are emitted from the user-defined source. If not setup, total loss rate (neutron transport, and total source rate is re-adjusted) or total source rate (photon transpor...
by Ana Jambrina
Fri Aug 14, 2020 4:12 pm
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

The activation integral can be seen as a response function coming from Serpent (also, you might want to take a look to activation detector (da)). Burnup steps are crucial to calculate nuclide concentrations. I do not see any problem coming from Serpent on how it calculates the activities. The issue ...
by Ana Jambrina
Fri Aug 14, 2020 1:15 pm
Forum: Bug reports
Topic: trans S s1 0 0 0 0.0 0.0 0.0000001 2 mirrors!
Replies: 5
Views: 1113

Re: trans S s1 0 0 0 0.0 0.0 0.0000001 2 mirrors!

It might be the case that what is happening with cylx is also happening with cyly, but it is not that obvious. When you set 0, there is not rotation at all, so, the cylinder keeps its original position. Maybe it is easier if you visually ‘split’ the transformation: For cylinder y: - (1) cylinder cen...
by Ana Jambrina
Thu Aug 13, 2020 4:54 pm
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

Giving a quick look to the input, some points here: - set gcu -1, non group constant generation is not needed. - unresolved resonances: set ures 1, is it needed or for comparison (on in MCNP by default) ? - normalisation: since an external source is used, what does it make more sense: power or srcra...
by Ana Jambrina
Thu Aug 13, 2020 11:18 am
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

Independently of what does or does not Serpent do, how did you calculate the activities?
by Ana Jambrina
Wed Aug 12, 2020 7:00 pm
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

Power set a normalisation to total fission power. Probably you are looking more to ‘srcrate’, source rate normalisation. During the irradiation, as said before, you might want to increase the number of steps. ‘gcut’ sets generation cut-off for neutrons, limiting the length of fission chains… For me,...
by Ana Jambrina
Wed Aug 12, 2020 3:50 pm
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

Maybe I am missing something here: you say that MCNP matches Serpent fluxes in each burnup step. That would mean your compositions should be consistent. But they are not, because activities are off. So, for me, it is one or another.
by Ana Jambrina
Wed Aug 12, 2020 2:55 pm
Forum: Users
Topic: material activation calculation
Replies: 15
Views: 2362

Re: material activation calculation

Fluxes and nuclide compositions are coupled in depletion calculations; then, those will define the activities. Did you compare MCNP fluxes with Serpent fluxes? Also, from your previous post: the depletion history you have setup probably is not capturing the physics behind - meaning, most likely your...
by Ana Jambrina
Wed Aug 12, 2020 12:04 pm
Forum: Users
Topic: about decstep daystep
Replies: 4
Views: 793

Re: about decstep daystep

Yes: you provide steps or time intervals when there is irradiation, followed by a downtime. However, you might want to refine the irradiation periods: time step length is an important parameter to consider during depletion calculations. You can see some examples about irradiation history in the Serp...