Rotational Symmetry in MCNPX core design

AI Thread Summary
Designing a PWR core in MCNPX with 4-fold rotational symmetry can significantly reduce computational time, but it requires careful consideration of power settings. When using reflective boundary conditions, the power should be reduced to 1/4th of the original 3000 MWth to accurately reflect the modeled geometry. MCNPX does not inherently recognize that only a portion of the core is being simulated, which necessitates this adjustment. In contrast, specialized codes for modeling LWR cores automatically adjust power based on symmetry, so users should consult the documentation for those tools. Properly managing power settings is crucial for accurate burnup calculations in MCNPX.
Perwaz Hussain
Designing a PWR core in MCNPX for burnup using 4 folds rotational symmetry to reduce computational time of the core, taking reflective boundary conditions on rotational symmetry planes. should the power be reduced to 1/4th of original power (3000 MWth) in burnup card or does the reflective boundary condition demands to give power as for the whole core i.e. 3000 MWth?
 
Engineering news on Phys.org
Short answer - reduce the power by 1/4th. MCNPX doesn't know enough about your geometry to know that you are only modeling 1/4 of the core.
(for example, you could be running 1/8th of a core with reflective boundary conditions).

There are codes that are specifically designed for modeling LWR cores. For these codes, you usually input the full-core power and the code
automatically adjusts the power depending on the symmetry. Read the code documentation for confirmation.
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
Back
Top