I thought I’d start a topic for anyone wanting to share a paper they wrote in which OpenMC was used, or if you came across a paper that used OpenMC.
Here’s one that I just came across using OpenMC for some studies on a lead-cooled reactor:
https://www.researchgate.net/publication/344376283_Investigation_of_a_Self-actuated_Gravity-driven_Shutdown_System_in_a_Small_Lead-cooled_Reactor
Here’s another one focused on the study of tritium breeding ratios in a fusion reactor:
Neutronic comparison of liquid breeders for ARC-like reactor blankets
SARAX: A new code for fast reactor analysis part I: Methods
On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX
Dear all,
I wrote a paper for this PHYSOR 2020, called: " Verification of the OpenMC homogenized MYRRHA-1.6 core model" https://publications.sckcen.be/portal/en/publications/verification-of-the-openmc-homogenized-myrrha16-core-model(422d637f-2685-479d-bb3e-217de2d7ad5d)/export.html
Is about XS homogenization for the research reactor known as MYRRHA. Thank you.
A recent paper by @Shimwell, @makeclean, and company:
High-speed generation of neutronics-ready CAD models for DEMO design
Nice paper using OpenMC to look into thermal scattering for U-Mo alloys:
Crystal binding effects on neutron scattering and criticality in U–Mo fuels
An interesting paper on a method for assessing source convergence that doesn’t rely on a mesh as our current Shannon entropy implementation does:
An effective mesh-free fission source convergence indicator for Monte Carlo k-Eigenvalue problems
A few recent papers: