Recent content by AlexFi

I keep getting particle lost error even though there were no hole in the lattice. Can someone identify any mistake in my code?

Thanks Alex A. I also added fm24 for fission rate tallying. Could you please check my code to make sure I put the right syntax for the multipliers? Is there any fm syntax or any code line for power density that can be used with fmesh?

Can someone give me a brief explanation what are imesh jmesh kmesh values are? edit: MCNP manual says IMESH is "Locations of the coarse mesh points in the y direction for rectangular geometry or in the x direction for cylindrical geometry" Which doesnt make any sense to me... what even is...

Sorry I didn't quite understand your answer. Yes, I will add volume definition in cell 3 and 4 in the code. My question is, how should I calculate the volume of each cell? For example, in cell 3, the coolant channels, should I put the volume of a single coolant channel or should I put the volume...

How should I define the volume? Should I put the volume of individual fuel elements, all fuel elements in the slice combined, or the volume of the slice itself?

I end up using F6 just to see my MCNP power output match the power output listed in the reference paper. MCNP give me an error every time I put cell 4 or 1 in the tally even though the fuel is located in those cells. Secondly, can someone help me interpret the tally output. As far as I can...

One other thing, is there an mcnp command that will automatically calculate total power output of a reactor?

rpp I'm transferring the power distribution (volumetric heat flux?) to star ccm. Planning to get it plotted, get a best-fit equation, and use that as a heat source in Star CCM+. I'm very new to MCNP. Can you explain what normalization is and how I do it in MCNP?

Thank you Correct me if I'm wrong, but I thought that F6 and F7 tally calculates total energy depositions in a cell. I wanted to map its radial and axial energy distribution to create a surface plot, which is why I use FMESH.

Hello I'm trying to use FMESH command to get power distribution of this core geometry. I want to use xyz coordinate in a 1/12 slice of a core so I could use the output of the MCNP sim for a CFD input How should I approach this? Thank you

I never learned how to use the lattice-universe thing properly How should I modify the code if I want to change the material of the elements in the perimeter of the core from helium to graphite?

Alex A Thank you so much I haven't tested your code yet, but here's the Lokhov paper. I just got it today

Made some minor changes, added void cell Still getting 'particle lost' and 'geometry error:no cell found' error message

I redid the atomic ratio & density calculation with graphite density of 1.77 g/cm^3 and I can only get k_eff down to 1.176 I cannot put .74c in the graphite because if I do so, I get 'cross section table missing' error Also how should I define cell 99?

Thanks for the explanation. It seems to me that MCNP deleted the entire cell and the simulation won't run because particles got lost. What would be a solution for this?