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Volume 186

Number 3

Inverse Predictive Modeling of Radiation Transport Through Optically Thick Media in the Presence of Counting Uncertainties

Dan Gabriel Cacuci

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 199-223

Technical Paper / dx.doi.org/10.1080/00295639.2017.1305244

Theoretical Convergence Rate Lower Bounds for Variants of Coarse Mesh Finite Difference to Accelerate Neutron Transport Calculations

Ang Zhu, Brendan Kochunas, Yunlin Xu, Michael Jarrett, Edward Larsen, Thomas Downar

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 224-238

Technical Paper / dx.doi.org/10.1080/00295639.2017.1293408

A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment

S. Santandrea, D. Sciannandrone, R. Sanchez, L. Mao, L. Graziano

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 239-276

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273634

Neutron Time Interval Distributions with Background Neutrons

Manoj Prasad, Neal Snyderman, Sean Walston

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 277-292

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273620

A Simple Iterative Method for Compensating the Response Delay of a Self-Powered Neutron Detector

Qingmin Zhang, Zhigang Hu, Bangjie Deng, Mengxuan Xu, Yuhang Guo

Nuclear Science and Engineering / Volume 186 / Number 3 / June 2017 / Pages 293-302

Technical Paper / dx.doi.org/10.1080/00295639.2016.1273619

 

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