Yousry Y Azmy

Hybrid approaches for accelerated convergence of block-Jacobi iterative methods for solution of the neutron transport equation

JOURNAL OF COMPUTATIONAL PHYSICS.

On the Regularity Order of the Pointwise Uncollided Angular Flux and Asymptotic Convergence of the Discrete Ordinates Approximation of the Scalar Flux

NUCLEAR SCIENCE AND ENGINEERING.

Solution of the Neutron Transport Equation on Unstructured Grids Using the Parallel Block Jacobi-Integral Transport Matrix Method via the Novel Green's Function ITMM Construction Algorithm on Massively Parallel Computer Systems

Hoagland, D. S., Yessayan, R. A., & Azmy, Y. Y. (2021, May 10). NUCLEAR SCIENCE AND ENGINEERING.

Asymptotic convergence of the angular discretization error in the scalar flux computed from the particle transport equation with the method of discrete ordinates

ANNALS OF NUCLEAR ENERGY, 138.

Sequential optimal positioning of mobile sensors using mutual information

STATISTICAL ANALYSIS AND DATA MINING.

Numerical convergence and validation of the DIMP inverse particle transport model

Nuclear Engineering and Technology, 49(6), 1358–1367.

Validation and uncertainty quantification of detector response functions for a 1″×2″ NaI collimated detector intended for inverse radioisotope source mapping applications

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 410, 1–15.

Recent studies on the asymptotic convergence of the spatial discretization for two-dimensional discrete ordinates solutions

Journal of Computational and Theoretical Transport, 45(4), 299–313.

Comparison of spatial discretization methods for solving the S-N equations using a three-dimensional method of manufactured solutions benchmark suite with escalating order of nonsmoothness

Nuclear Science and Engineering, 180(1), 1–29.

Iterative stability analysis of spatial domain decomposition based on block Jacobi algorithm for the diamond-difference scheme

Journal of Computational Physics, 297, 462–479.

Radiation source mapping with Bayesian inverse methods

Nuclear Science and Engineering, 179(4), 364–380.

Using the Cartesian Discrete Ordinates code DORT for assembly-level calculations

Nuclear Science and Engineering, 173(3), 233–258.

A Robust arbitrarily high-order transport method of the characteristic type for unstructured grids

Nuclear Science and Engineering, 172(1), 33–51.

Newton's method for solving k-eigenvalue problems in neutron diffusion theory

Nuclear Science and Engineering, 167(2), 141–153.

Newton's method for the computation of k-Eigenvalues in S-N transport applications

Nuclear Science and Engineering, 168(1), 37–58.

On the degradation of cell-centered diffusive preconditioners for accelerating S-N transport calculations in the periodic horizontal interface configuration

Nuclear Science and Engineering, 166(3), 218–238.

A posteriori error estimator and AMR for discrete ordinates nodal transport methods

Annals of Nuclear Energy, 36(3), 268–273.

Properties of the S-N-equivalent integral transport operator in slab geometry and the iterative acceleration of neutral particle transport methods

Nuclear Science and Engineering, 162(3), 234–252.

Spatial convergence study of discrete ordinates methods via the singular characteristic tracking algorithm

Nuclear Science and Engineering, 162(1), 41–55.

TORT solutions to the NEA suite of benchmarks for 3D transport methods and codes over a range in parameter space

Annals of Nuclear Energy, 36(3), 368–374.

Computational modelling of genome-side transcription assembly networks using a fluidics analogy

PLoS One, 3(8).

Comparison via parallel performance models of angular and spatial domain decompositions for solving neutral particle transport problems

Progress in Nuclear Energy, 49(1), 37–60.

Modeling and optimization of existing beam port facility of PSBR

Annals of Nuclear Energy, 33(17-18), 1391–1395.

Tort solutions to the three-dimensional MOX benchmark, 3-D Extension C5G7MOX

Progress in Nuclear Energy, 48(5), 445–455.

Dort solutions to the two-dimensional C5G7MOXbenchmark problem

Progress in Nuclear Energy, 45(2-4), 215–231.