1. A 2-D/1-D Transverse Leakage Approximation Based on Azimuthal, Fourier Moments. (1st February 2017) Authors: Stimpson, Shane; Collins, Benjamin; Downar, Thomas Journal: Nuclear science and engineering Issue: Volume 185:Number 2(2017) Page Start: 243 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations. (3rd October 2018) Authors: Faure, Bastien; Archier, Pascal; Vidal, Jean-François; Buiron, Laurent Journal: Nuclear science and engineering Issue: Volume 192:Number 1(2018) Page Start: 40 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
3. A CFD Modeling Coupled with VOF Method and Solidification Model for Molten Jet Breakup at Low Velocity. (4th March 2023) Authors: Liu, Tao; Zhou, Yuan; Zhong, Mingjun; Gong, Houjun Journal: Nuclear science and engineering Issue: Volume 197:Number 3(2023) Page Start: 398 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
4. A CMFD Acceleration Method for SP3 Advanced Nodal Method. (1st October 2016) Authors: Yamamoto, Akio; Sakamoto, Tatsuya; Endo, Tomohiro Journal: Nuclear science and engineering Issue: Volume 184:Number 2(2016) Page Start: 168 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
5. A Coarse-Mesh Coupled Neutronics and Thermal Fluids Method for Prismatic Cores. (1st October 2016) Authors: Connolly, Kevin John; Huning, Alexander J.; Rahnema, Farzad; Garimella, Srinivas Journal: Nuclear science and engineering Issue: Volume 184:Number 2(2016) Page Start: 228 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
6. A Coarse-Mesh Diffusion Synthetic Acceleration Method with Local hp Adaptation for Neutron Transport Calculations. (2nd November 2018) Authors: Byambaakhuu, Tseelmaa; Wang, Dean; Xiao, Sicong Journal: Nuclear science and engineering Issue: Volume 192:Number 2(2018) Page Start: 208 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
7. A Code-Agnostic Driver Application for Coupled Neutronics and Thermal-Hydraulic Simulations. (3rd April 2021) Authors: Romano, Paul K.; Hamilton, Steven P.; Rahaman, Ronald O.; Novak, April; Merzari, Elia; Harper, Sterling M.; Shriwise, Patrick C.; Evans, Thomas M. Journal: Nuclear science and engineering Issue: Volume 195:Number 4(2020) Page Start: 391 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
8. A Comparison Between the Embedded Self-Shielding Method and the Enhanced Neutron Current Method Based on the Equivalent Pin Cell Model on the Irregular Fuel Lattice Problem. (3rd March 2020) Authors: Zhang, Qian; Liang, Liang; Zhao, Qiang; Zhang, Zhijian; Wu, Hongchun; Cao, Liangzhi Journal: Nuclear science and engineering Issue: Volume 194:Number 3(2020) Page Start: 232 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
9. A Computationally Viable Version of the PN Method for Spheres. (4th May 2017) Authors: Garcia, R. D. M.; Siewert, C. E.; Thomas, J. R. Journal: Nuclear science and engineering Issue: Volume 186:Number 2(2017) Page Start: 103 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
10. A Consistent CMFD Formulation for the Acceleration of Neutron Transport Calculations Based on the Finite Element Method. (1st February 2017) Authors: Jung, Yeon Sang; Yang, Won Sik Journal: Nuclear science and engineering Issue: Volume 185:Number 2(2017) Page Start: 307 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗