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@ -196,9 +196,14 @@ Miscellaneous
Reaction Rate Kernel Density Estimators in OpenMC," *Trans. Am. Nucl. Soc.*,
**109**, 683-686 (2013).
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Multi-group Cross Section Generation
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Multigroup Cross Section Generation
-----------------------------------
- William Boyd, Benoit Forget, and Kord Smith, "`A single-step framework to
generate spatially self-shielded multi-group cross sections from Monte Carlo
transport simulations <https://doi.org/10.1016/j.anucene.2018.11.017>`_,"
*Ann. Nucl. Energy*, **125**, 261-271 (2019).
- Changho Lee and Yeon Sang Jung, "Verification of the Cross Section Library
Generated Using OpenMC and MC\ :sup:`2`-3 for PROTEUS," *Proc. PHYSOR*, Cancun,