# What’s New in 0.11.0¶

## Summary¶

This release of OpenMC adds several major new features: depletion, photon transport, and support for CAD geometries through DAGMC. In addition, the core codebase has been rewritten in C++14 (it was previously written in Fortran 2008). This makes compiling the code considerably simpler as no Fortran compiler is needed.

Functional expansion tallies are now supported through several new tally filters that can be arbitrarily combined:

Note that these filters replace the use expansion scores like scatter-P1. Instead, a normal scatter score should be used along with a openmc.LegendreFilter.

The interface for random sphere packing has been significantly improved. A new openmc.model.pack_spheres() function takes a region and generates a random, non-overlapping configuration of spheres within the region.

## Python API Changes¶

• All surface classes now have coefficient arguments given as lowercase names.

• The order of arguments in surface classes has been changed so that coefficients are the first arguments (rather than the optional surface ID). This means you can now write:

x = openmc.XPlane(5.0, 'reflective')
zc = openmc.ZCylinder(0., 0., 10.)

• The Mesh class has been renamed openmc.RegularMesh.

• The get_rectangular_prism function has been renamed openmc.model.rectangular_prism().

• The get_hexagonal_prism function has been renamed openmc.model.hexagonal_prism().

• Python bindings to the C/C++ API have been move from openmc.capi to openmc.lib.

## Contributors¶

This release contains new contributions from the following people: