Recent content by nuclearsneke

Hello there. I have been conducting a thermal calculation of a fuel assembly for KLT-40S reactor (a small modular PWR-like reactor installed at the floating nuclear power plant "Akademik Lomonosov" with electric power of 35 MWe.) and obtained some interesting results. It seems that cladding...

Actually, i am studying questions of fuel lifetime extension right now. If you want fuel to be utilized longer, you may be interested in use of thorium-based fuel as it builds up u233, a fissile material, and also produces less transuranic waste. However, u233 has gradually lower delayed...

Hi there I want to convert the flux (F4:N tally) from mcnp units to cm-2s-1 units. How to do that? Also I have some bug in MCNPX: while running the file, I get an error like " >bad trouble in imcn in routine xin >Cannot find bertin " How to solve it? Database for MCNP5-MCNPX got installed already.

Hi, I am interested in simulation of parallel beams for neutrons and photons (separately of course). Any ideas on how to simulate them in MCNP5 or MCNPX?

Howdie! We have been playing around with melting and molding HDPE pellets recently. After that, we measured their diameter and thickiness 5 times each to get an uncertainty. In our experiments we put one pellet between gamma-source and detector and measure its attenuation. After that we place...

Nope, I am but a merely fan of cyberpunk2077 and its slang :)

I know about jacobians. If my B_phi is 0, then I can just put my B(Br,0,Bz) as B(Bx,0,Bz)? I will only have neutron leakage in x-axis and in z axis. That's preem!

Good day! I am currently struggling with a very trivial question. During my studies, I operated with a parameter called "geometrical buckling" for neutrons and determined it in cylindrical coordinates. But thing is that we usually do not consider buckling's dependence on angle so its angular...

N/v for fuel is (rho_fuel*N_a/M(th232*(1-0.0366)+u233*(0.0366))) N/v for u233 is n/v_fuel*0.0366 N/v for th232 is n/v_fuel*(1-0.0366) These quantities will be in cm^-3

Wow. Given that I had a material science course mostly focused on phase diagrams and lattice types, I have never heard of that preem law/rule of mixture. Now the problem I mentioned above looks so trivial... Thank you, Astronuc!

I get it that density of fuel would be low due to its dispersion in alloy. But is there any way to calculate a density of fuel pellet starting from this "uranium density in fuel kernel" value?

I hab this one but no luck :(

There is a Russian code named Mcu with a shitton of functions. I can share it for you but documentation is in Russian. Write me in PM if you are interested.

Howdy partners! I am currently doing some project on Klt40s neutronic simulation (you might have heard of Akademik Lomonosov, the floating npp). But I have encountered a problem with fuel density. The only info that i got that "uranium density IN FUEL MEAT/KERNEL" is 4.5 g/cm3. The Fuel is...

Howdy, my fellow nuclear colleagues! I am new to MCNP5 and currently I am trying to simulate something simple like a sphere of UO2 to calculate its critical size. Whenever I run my file via MCNP5 or Vised, I get an error message like bad trouble in subroutine pass1 of imcn...