Search found 73 matches

by Yousef1986
Wed Sep 20, 2017 10:00 am
Forum: Users
Topic: Number of nuclides in depletion calculation
Replies: 4
Views: 1665

Re: Number of nuclides in depletion calculation

Thanks Jaakko for the clarification
by Yousef1986
Tue Sep 19, 2017 3:38 pm
Forum: Users
Topic: Number of nuclides in depletion calculation
Replies: 4
Views: 1665

Re: Number of nuclides in depletion calculation

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?
by Yousef1986
Tue Sep 19, 2017 10:01 am
Forum: Users
Topic: Number of nuclides in depletion calculation
Replies: 4
Views: 1665

Number of nuclides in depletion calculation

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
by Yousef1986
Thu Jun 22, 2017 12:57 pm
Forum: Users
Topic: Power Distribution for each burnup step using SIE method
Replies: 2
Views: 1175

Re: Power Distribution for each burnup step using SIE method

Hi Ville,

I have modified the if-statement on line 531 and 551 of score.c to skip the return statement in the case of SIE method and now it works fine.
Thanks for the advice.
by Yousef1986
Wed Jun 21, 2017 2:48 pm
Forum: Users
Topic: Power Distribution for each burnup step using SIE method
Replies: 2
Views: 1175

Power Distribution for each burnup step using SIE method

Dear Jaakko, I am trying to print power distribution using "set cpd" card at each burnup step. I am using the SIE method for the depletion and got the following problem: The power distribution is printed only at fresh calculation (i.e. zero burnups and at the predictor step only) and as you know the...
by Yousef1986
Sat Jun 03, 2017 5:33 pm
Forum: Users
Topic: Spatial distribution of Xe-135
Replies: 2
Views: 985

Re: Spatial distribution of Xe-135

Thanks Jaakko
Interesting to know that with "set depout 1" I could get zone-wise composition into the _dep.m output file.
That what I was looking for :)
by Yousef1986
Thu Jun 01, 2017 12:51 pm
Forum: Users
Topic: Spatial distribution of Xe-135
Replies: 2
Views: 985

Spatial distribution of Xe-135

Dear Jaakko,

Is there a way to print out the distribution of Xe-135 atomic density in 3D geometry and as a function of burnup.
by Yousef1986
Tue Mar 07, 2017 4:09 pm
Forum: Users
Topic: Printing output files in a different directory
Replies: 1
Views: 1033

Printing output files in a different directory

Dear Jaakko,

Is there a way to specify the path where I want Serpent to print output files such as _res.m, .out, .seed, etc.
It would be useful to have such a flexibility.
by Yousef1986
Mon Feb 13, 2017 7:08 pm
Forum: Users
Topic: Fatal error in function MatPtr
Replies: 6
Views: 4007

Re: Fatal error in function MatPtr

Dear Jaakko Sorry for the late followup. I tried what you have suggested by changing divide material card to div UO2 sep 3 for pin level depletion and it worked for the UO2 pins. However, I have burnable poison pins (Al2O3B4C) and when including div Al2O3B4C sep 3 to undergo depletion, it gives the ...
by Yousef1986
Thu Dec 22, 2016 2:07 pm
Forum: Users
Topic: Serpent RIA Simulation
Replies: 1
Views: 819

Serpent RIA Simulation

Dear Jaakko,

Out of curiosity, Is it possible to perform RIA simulation using Serpent? Is there any published paper in this regard?