Search found 7 matches

by josejavier
Fri Jan 09, 2015 2:15 pm
Forum: Users
Topic: ENDF/B-VII thermal libraries lwtr
Replies: 1
Views: 912

Re: ENDF/B-VII thermal libraries lwtr

Hello,

The lwtr.20t file is the new continuous energy version of the thermal libraries, I think you should use the lwtr.10t to lwtr.18t files which have discrete energy information for it to work with SERPENT.
Hope it helps.

Regards.
by josejavier
Thu Jul 17, 2014 11:37 am
Forum: Bugs, problems, questions & feeback
Topic: ENDF-B-VII.1 - problem with adding nuclides in material
Replies: 14
Views: 6603

Re: ENDF-B-VII.1 - problem with adding nuclides in material

Hi!

I do not know if this is your situation, but the ACE files coming with MCNP distribution now include 2 additional lines at the top, and this is causing SERPENT2 to get stuck like you mentioned. You should eliminate those lines on the ACE files or modify the source.

Regards.
by josejavier
Wed Apr 16, 2014 5:34 pm
Forum: Bugs, problems, questions & feeback
Topic: total exceeds majorant error in SF problem
Replies: 10
Views: 12030

Re: total exceeds majorant error in SF problem

Hi, I can not run my problem on SERPENT1 so for SERPENT2 always with same input: - 2.1.13 fails with same error on tracking - 2.1.16 fails with same error on tracking. - 2.1.20 with debugging fails also - I am not using optimizations or grid thinning. - I am using both JEFF-3.2 and ENDF/B-7.1 for ev...
by josejavier
Wed Apr 16, 2014 11:54 am
Forum: Bugs, problems, questions & feeback
Topic: thermal scattering U in UO2 plus burnup
Replies: 1
Views: 1827

thermal scattering U in UO2 plus burnup

Hi, Recently I tried including the thermal scattering data for uranium in UO2 in some calculations. Criticality calculations are working properly, but I started a burn-up/depletion calculation where I get the following error message: Burning material: 0% complete ***** Wed Apr 16 10:45:09 2014 (seed...
by josejavier
Wed Apr 16, 2014 11:37 am
Forum: Development
Topic: setup initial isotopes concentrations
Replies: 2
Views: 1063

Re: setup initial isotopes concentrations

Thanks! It worked of course
by josejavier
Wed Apr 16, 2014 11:22 am
Forum: Bugs, problems, questions & feeback
Topic: total exceeds majorant error in SF problem
Replies: 10
Views: 12030

total exceeds majorant error in SF problem

Hello, I am simulating a spent fuel canister and I started to look at the fuel "depletion" when only the spontaneous neutron fission source is considered in the problem. So I run a burn-up/depletion problem with an external source equal to zero, thus only this fission neutrons are taken as source te...
by josejavier
Thu Jan 09, 2014 6:17 pm
Forum: Development
Topic: setup initial isotopes concentrations
Replies: 2
Views: 1063

setup initial isotopes concentrations

Hello, At present, I am performing decay calculations for spent fuel for long time periods (hundreds to thousands of years) using the compositions from the NEA benchmark on BUC-Phase VII, and I am using SERPENT2 as a decay code with the options 'decstep' or 'dectot' as coupled flux calculations are ...