Closed andrewryh closed 5 years ago
@andrewryh Hello, The burnup time extended to 60 yrs and the statistical error decreased to 35 pcm, some results uploaded in this link; https://github.com/osamamala/saltproc-validation/tree/master/SD-TMSR/doc/plots_60_years_using_SERPENT
for output files, please see; https://github.com/osamamala/saltproc-validation/tree/master/SD-TMSR/serpent/60-years-analysis
I hope you can start to calculate the temperature coefficients of reactivity, power and breeding distribution, six factors formula parameters as soon as possible while I modify the manuscript with the new results. Also, I will send you the reprocessing scheme which I used in this simulation in order to add it in SaltProc so that we will be able to verify the SaltProc against the SERPENT built-in mode in SD-TMSR in the near future.
best Osama
@osamamala Cool, very pretty results, I'm pretty happy with uncertainty you've obtained and special thanks for this plot: https://github.com/osamamala/saltproc-validation/blob/master/SD-TMSR/doc/plots_60_years_using_SERPENT/dm%25.png This is awesome, you must include it in the manuscript.
Indeed, I can now go ahead and calculate the temperature coefficients of reactivity, power and breeding distribution, six factors formula parameters. Please, send me by email your latest input file (I have a geometry file, but I need a neutron population/active-inactive/cycles, libraries you've used, etc), and I will start my part immediately.
Meanwhile, you can modify manuscript and revise it carefully. Then, I will include my results in it, review the whole manuscript, and then will ask @katyhuff for review. Also, @katyhuff, hopefully, will help to determine in which journal we can submit it.
Good work!
@osamamala I started calculating thermal feedback and have few questions about your TCR calculations:
1) Fuel salt density for 900K is 3.3g/cm3 (it is from your and Chinese paper). Did you estimate density change using Dilatation co-efficiency of fuel (g/(cm3⋅K)) from their paper?
2) Have you changed graphite density or kept it 2.3g/cm3 for all temperatures?
3) Have you changed graphite elements linear dimensions (because they will expand as temperature rise)?
4) Why you used therm graphiteLib grj3.00t
in line 28? This is means using thermal scattering libraries for graphite for temperature 294K. Have you changed this line when changed the temperature of graphite for TCR calculation?
I got -0.8pcm/K, so, trying to understand your and Chinese guys approach...
@andrewryh
1] Yes, I used the Dilatation co-efficiency of fuel (-6.7E-4) to calculate the change of density for, 900 ==> 3.3 g/cc 960 ==> 3.26 1015 ==> 3.23 1075 ==> 3.2 1130 ==>3.14 and calculate the TCR using P= (dKeff/keff.dT)*10^5= [pcm/k].
2] kept it constant 2.3 g/cc.
3] I neglected the expansion of the graphite elements. 4] No I didn't change line 28.
Li paper says:
The total TCR includes the graphite TCR and the molten salt TCR, and the latter consists of the Doppler effect and the density effect.
So, I am considering separately this 3 factors of thermal feedback:
Neglecting graphite density and linear dimensions change (no data for this sort of graphite). For MSBR Graphite density and thermal expansion effect is about +0.14pcm/K for initial and +0.23pcm/K for equilibrium compositions.
2.3g/cc is very strength density fo graphite. Crystal density of graphite 2.225 g/cc at 294K. So, for 900K it should be less than 2.225g/cc even if they indent to grow a single crystal for each graphite element.
@andrewryh Hi, Results after thermal scattering data correction ==> https://github.com/osamamala/saltproc-validation/tree/master/SD-TMSR/doc/plots_60_years_using_SERPENT output files as usual in this link; https://github.com/osamamala/saltproc-validation/tree/master/SD-TMSR/serpent/60-years-analysis
the latest input file will be sent to you by email. thanks
@osamamala Looks good to me. I have done simulations and visualization for initial fuel case. Plots here: https://github.com/arfc/saltproc-validation/tree/master/SD-TMSR/doc/plots_initial_comp_safety_param
The output here: https://github.com/arfc/saltproc-validation/tree/master/SD-TMSR/safety_parameters
The plotter is here: https://github.com/arfc/saltproc-validation/blob/master/SD-TMSR/plotters/SERPENT2_depleted_composition_ploter.ipynb
@andrewryh Looks good to me. the neutron spectrum for a different time here; https://github.com/osamamala/saltproc-validation/blob/master/SD-TMSR/doc/plots_60_years_using_SERPENT/spectrum.png
it is enough or should I run 18, 20... etc?
thanks
@andrewryh Hi, Andrei, please, could you explain how you calculated the reactivity coefficient for Total core. Did you increase the whole reactor temperature from 900K to 1000K? Did you notice that -0.98 is not a high negative temperature coefficient or it is normal for the initial case?
@osamamala
1) Yes, could you please make it for 20, 40, 60 years? Then we should select 4 most interesting spectra.
2) I ran simulation for 900K everywhere, then for 1000K (I changed fuel density and temperature, graphite temperature and thermal scattering temperature). Robertson for MSBR calculated -0 87pcm/K for initial. So, it is looks realistic. Your and Like coefficient has been obtained without changing thermal scattering cross section library temperature...
Will see what I obtain for equilibrium. I think it will be worse.
As you can see, graphite Doppler is positive and large. That's why we don't build RBMK anymore...
@andrewryh
@andrewryh
The neutron flux for initial, 20, 22 and 24 years here; https://github.com/osamamala/saltproc-validation/blob/master/SD-TMSR/doc/plots_60_years_using_SERPENT/spectrum.png
the spectrum is almost didn't change.
So, I gonna make the following simulations for this paper: