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@ -146,10 +146,25 @@ Geometry and Visualization
Miscellaneous
-------------
- Ned Xoubi, Sharif Abu Darda, Abdelfattah Y. Soliman, and Tareq Abulfaraj,
- Sharif Abu Darda, Abdelfattah Y. Soliman, Mohammed S. Aljohani, and Ned Xoubi,
"`Technical feasibility study of BAEC TRIGA reactor (BTRR) as a neutron source
for BNCT using OpenMC Monte Carlo code
<https://doi.org/10.1016/j.pnucene.2020.103418>`_", *Prog. Nucl. Energy*,
**126**, 103418 (2020).
- Stefano Segantin, Raffaella Testoni, and Massimo Zucchetti, "`ARC reactor --
Neutron irradiation analysis <https://doi.org/10.1016/j.fusengdes.2020.111792>`_",
*Fus. Eng. Design*, **159**, 111792 (2020).
- Muhammad Ilham, Helen Raflis, and Zaki Suud, "`Full Core Optimization of Small
Modular Gas-Cooled Fast Reactors Using OpenMC Program Code
<https://doi.org/10.1088/1742-6596/1493/1/012007>`_", *J. Phys.: Conf. Series*,
**1493**, 012007 (2020).
- Ned Xoubi, Sharif Abu Darda, Abdelfattah Y. Soliman, and Tareq Abulfaraj,
"`An investigative study of enrichment reduction impact on the neutron flux in
the in-core flux-trap facility of MTR research reactors
<https://doi.org/10.1016/j.net.2019.08.008>`_", Nucl. Eng. Technol., **52**,
<https://doi.org/10.1016/j.net.2019.08.008>`_", *Nucl. Eng. Technol.*, **52**,
469-476 (2020).
- J. Rolando Granada, J. Ignacio Marquez Damian, and Christian Helman, "`Studies
@ -162,6 +177,10 @@ Miscellaneous
<https://doi.org/10.13140/RG.2.2.26088.01281>`_," M.S. Thesis, KTH Royal
Institute of Technology (2019).
- Ilham Variansyah, Benjamin R. Betzler, and William R. Martin,
":math:`\alpha`\ -weighted transition rate matrix method", *Proc. M&C*,
1368-1377, Portland, Oregon, Aug. 25-29 (2019).
- Shikhar Kumar, Benoit Forget, and Kord Smith, "Analysis of fission source
convergence for a 3-D SMR core using functional expansion tallies," *Proc.
M&C*, 937-947, Portland, Oregon, Aug. 25-29 (2019).
@ -249,6 +268,16 @@ Miscellaneous
Multigroup Cross Section Generation
-----------------------------------
- Ilham Variansyah, Benjamin R. Betzler, and William R. Martin, "`Multigroup
Constant Calculation with Static :math:`\alpha`\ -Eigenvalue Monte Carlo for
Time-Dependent Neutron Transport Simulation
<https://doi.org/10.1080/00295639.2020.1743578>`_", *Nucl. Sci. Eng.*, 2020.
- Chenghui Wan, Tianliang Hu, and Liangzhi Cao, "`Multi-physics numerical
analysis of the fuel-addition transients in the liquid-fuel molten salt reactor
<https://doi.org/10.1016/j.anucene.2020.107514>`_", *Ann. Nucl. Energy*,
**144**, 107514 (2020).
- William Boyd, Adam Nelson, Paul K. Romano, Samuel Shaner, Benoit Forget, and
Kord Smith, "`Multigroup Cross-Section Generation with the OpenMC Monte Carlo
Particle Transport Code <https://doi.org/10.1080/00295450.2019.1571828>`_,"