Volume 193
Number 8
Iteration Methods with Multigrid in Energy for Eigenvalue Neutron Diffusion Problems
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 803-827
Technical Paper / dx.doi.org/10.1080/00295639.2019.1573601
Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 828-853
Technical Paper / dx.doi.org/10.1080/00295639.2018.1560854
Calculating Time Eigenvalues of the Neutron Transport Equation with Dynamic Mode Decomposition
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 854-867
Technical Paper / dx.doi.org/10.1080/00295639.2018.1565014
A New Approach to Monte Carlo in High Temperature Reactors
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 868-883
Technical Paper / dx.doi.org/10.1080/00295639.2019.1576453
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 884-902
Technical Paper / dx.doi.org/10.1080/00295639.2019.1573602
Tantalum, Titanium, and Zirconium Neutron Total Cross-Section Measurements from 0.4 to 25 MeV
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 903-915
Technical Paper / dx.doi.org/10.1080/00295639.2019.1570750
Nuclear Science and Engineering / Volume 193 / Number 8 / August 2019 / Pages 916-925
Technical Paper / dx.doi.org/10.1080/00295639.2019.1574118
