diff --git a/docs/source/publications.rst b/docs/source/publications.rst index a6746741e..83b0ffe07 100644 --- a/docs/source/publications.rst +++ b/docs/source/publications.rst @@ -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 + `_", *Prog. Nucl. Energy*, + **126**, 103418 (2020). + +- Stefano Segantin, Raffaella Testoni, and Massimo Zucchetti, "`ARC reactor -- + Neutron irradiation analysis `_", + *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 + `_", *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 - `_", Nucl. Eng. Technol., **52**, + `_", *Nucl. Eng. Technol.*, **52**, 469-476 (2020). - J. Rolando Granada, J. Ignacio Marquez Damian, and Christian Helman, "`Studies @@ -162,6 +177,10 @@ Miscellaneous `_," 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 + `_", *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 + `_", *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 `_,"