Recent content by emilmammadzada

Hello everyone, I am working on implementing a 2D Monte Carlo neutron transport simulation based on the methodology described in this thesis: https://scholarcommons.sc.edu/cgi/viewcontent.cgi?article=6511&context=etd I adapted the code to simulate neutron transport through a fuel pin with...

Dear expert, I am trying to design a hexagonal smr type reactor. My reactor k_eff starts to decrease rapidly after 20 days, for example from 1.2 to 0.8. What edits do you suggest to prevent this? I have attached the serpent input file below .How can I make appropriate optimizations for this reactor?

So what I want to understand here is how to calculate the total thermal power for a SMR and a normal reactor. How does the number of fuel pins or fuel volume affect it?

Hello Dear Experts. I need help with the calculation of total thermal power in nuclear reactors. Can someone explain the general mathematical approach or provide useful formulas for this calculation? Thanks!

Dear Experts I would like to create a small modular reactor-like geometry for Serpent code (example: ABV reactor). How can I add a control rod to the center like in the picture below? Which code scripts should I add in the geometry part. And how can I do this in Hexagonal laticce?

I have shared the links related to the issue below. SMR progression problem link-https://serpent.vtt.fi/mediawiki/index.php?title=Kraken_SMR_progression_problem Serpent Manual PDF https://serpent.vtt.fi/download/Serpent_manual.pdf

This seems to be the definition of material in serpent. I calculated it by applying what was written in this section at first. I could not find the reason why x10 was different. "Material name is used to identify the material in cell cards (see Sec. 3.3.1 on page 25). Thenuclide names...

I performed the atomic density calculations as you suggested, but the results were ten times different from the data in the Serpent sample file. I hope your calculation of these values will also be insightful for me. Thank you again!

How do I do the calculation in this case, what steps do I follow to calculate atomic densities?

I have attached the original ppm file below. I think there is no shift here. I don't know where the calculation error is coming from.

Serpent Data Calculate Data O-16.03c 3.32E-01 O-16.03c 3.31E-02 O-17.03c 1.27E-04 O-17.03c 1.28E-05 O-18.03c 6.83E-04 O-18.03c 6.64E-05 H-1.03c 6.66E-01 H-1.03c 6.64E-02 H-2.03c 7.66E-05 H-2.03c 9.96E-06 B-10.03c 8.29E-05 B-10.03c 8.19E-06 B-11.03c 3.34E-04 B-11.03c 3.35E-05 Dear...

Dear expert, I did not understand how the calculations for Boron isotopes were made here. The values B-10.03c 8.293027e-05 and B-11.03c 3.338047e-04 How to calculate. Can you do the calculations you did for water for Boron?

Hello everyone, I am trying to calculate the atomic density (in atom/barn-cm) for borated water (750 ppm) at 300 K in the active core of a reactor. Could anyone guide me on the correct approach or provide a reference formula for this calculation? I came across the following atomic densities (in...

I got this data from the serpent nuclear code input file. There was no fuel density given there, I just wonder how the content of such fuels is calculated. There is no information about density here % --- 2D SFR Assembly based on MET-1000 % --- Materials mat fuel sum tmp 807.15 vol...

Isn't it separate for uranium and separate for neptunium in this composition?