Search found 27 matches

by ondrejch
Wed Mar 31, 2021 11:28 pm
Forum: Bugs, problems, questions & feeback
Topic: Calculating radiation exposure in an MSR – radioactive source problem
Replies: 3
Views: 385

Re: Calculating radiation exposure in an MSR – radioactive source problem

Dear Ana, thank you for your response. I believe I follow the two steps you mentioned, with the two input deck I posted. The fuel material is not divided. Thanks for catching the material volume typo, I had the testwire and fuel volumes switched. I changed the line 16 of 'wire' to burn 0, as you sug...
by ondrejch
Mon Mar 29, 2021 9:42 pm
Forum: Bugs, problems, questions & feeback
Topic: Calculating radiation exposure in an MSR – radioactive source problem
Replies: 3
Views: 385

Calculating radiation exposure in an MSR – radioactive source problem

Dear Serpent users and developers. I would like to calculate transmutations somewhere in an MSR loop. This appears as a two-step process: 1) effects of neutrons from the core fission, 2) effects of delayed neutrons from the flowing salt. The first step is conceptually straight forward, just run the ...
by ondrejch
Tue Mar 16, 2021 11:33 pm
Forum: Bug reports
Topic: JEFF-3.3 Fatal error in function ProcessEDistributions
Replies: 2
Views: 302

Re: JEFF-3.3 Fatal error in function ProcessEDistributions

Dear Ana, thank you for a prompt reply. I re-downloaded the data from https://www.oecd-nea.org/dbdata/jeff/jeff33/index.html and it all works now splendidly. Apparently the problem was with the old data.
by ondrejch
Sun Mar 14, 2021 10:42 pm
Forum: Bug reports
Topic: JEFF-3.3 Fatal error in function ProcessEDistributions
Replies: 2
Views: 302

JEFF-3.3 Fatal error in function ProcessEDistributions

I switched from ENDF-VII to JEFF-3.3 and got this error while reading in the cross sections. Serpent version 2.1.32. No problems with JEFF-311, ENFD-VII, ENDF-VIII. ... Processing cross sections and ENDF reaction laws... ... Nuclide 61147.02c -- promethium 147 at 900K (Pm-147) Nuclide 61148.02c -- p...
by ondrejch
Tue Mar 17, 2020 7:30 pm
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Re: Set axis range for plots

Jaakko, they are a part of geometry, everything is +- reasonable. I emailed you the input file.
by ondrejch
Sat Mar 14, 2020 5:23 am
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Re: Set axis range for plots

Interesting. The salt is burned, its volume is set, and the only processing is an off-gas. I will email Jaakko.
by ondrejch
Thu Mar 12, 2020 3:30 pm
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Re: Set axis range for plots

Here is the example: https://msr.ne.utk.edu/~o/test_dep.m

Code: Select all

fd=serpentTools.read("test_dep.m")
s=fd.materials['salt']
s.plot('burnup','adens',names=['U235','Pu239'])
by ondrejch
Thu Mar 12, 2020 7:29 am
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Re: Set axis range for plots

Thanks Andrew for your reply.

Serpent tools:

Code: Select all

In [62]: serpentTools.__version__
Out[62]: '0.9.2'
Serpent is Version 2.1.31

Python (in spyder3)

Code: Select all

Python 3.7.5 (default, Nov 20 2019, 09:21:52)
IPython 5.8.0 -- An enhanced Interactive Python.
by ondrejch
Wed Mar 11, 2020 7:20 pm
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Material has no burnup

For some reason when the material is selected, fuel=dep.materials['fuel0'], fuel.burnup is an array full of zeros, while fuel.days has the correct array of nonzero depletion steps.

This can be fixed by fuel.data['burnup'] = dep.metadata['burnup']
by ondrejch
Wed Mar 11, 2020 6:28 pm
Forum: serpentTools
Topic: Set axis range for plots
Replies: 9
Views: 2099

Re: Set axis range for plots

It seems I figured it out. Either, while plotting, one can adjust one axis only: res.plot('burnup', ['absKeff', 'colKeff']).set_xlim([min,max]) res.plot('burnup', ['absKeff', 'colKeff']).set_ylim([min,max]) Or one can get the matplotlib.axes object, fix it up, and replot: fig=res.plot('burnup', ['ab...