Yousry Azmy: search on Z-Library

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1

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

Hu, Xiaoyu, Azmy, Yousry Y.

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 985 KB

english, 2020

2

Arbitrarily high order characteristic methods for solving the neutron transport equation

Journal:

Annals of Nuclear Energy

Year:

1992

Language:

english

File:

PDF, 989 KB

english, 1992

3

Modeling and optimization of existing beam port facility of PSBR

Fatih Alim, Kursat Bekar, Kostadin Ivanov, Kenan Unlu, Jack Brenizer, Yousry Azmy

Journal:

Annals of Nuclear Energy

Year:

2006

Language:

english

File:

PDF, 719 KB

english, 2006

4

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

Kursat B. Bekar, Yousry Y. Azmy

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 475 KB

english, 2009

5

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

Jose I. Duo, Yousry Y. Azmy, Ludmil T. Zikatanov

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 1.63 MB

english, 2009

6

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

Jesse J. Klingensmith, Yousry Y. Azmy, Jess C. Gehin, Roberto Orsi

Journal:

Progress in Nuclear Energy

Year:

2006

Language:

english

File:

PDF, 520 KB

english, 2006

7

A posteriori error estimation for the one-dimensional arbitrarily high-order transport-nodal method

Oscar M. Zamonsky, Gustavo C. Buscaglia, Yousry Y. Azmy

Journal:

Annals of Nuclear Energy

Year:

2000

Language:

english

File:

PDF, 1.06 MB

english, 2000

8

Performance and performance modeling of a parallel algorithm for solving the neutron transport equation

Journal:

The Journal of Supercomputing

Year:

1992

Language:

english

File:

PDF, 1.44 MB

english, 1992

9

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

Anistratov, Dmitriy Y., Azmy, Yousry Y.

Journal:

Journal of Computational Physics

Year:

2015

Language:

english

File:

PDF, 2.35 MB

english, 2015

10

Sequential optimal positioning of mobile sensors using mutual information

Schmidt, Kathleen, Smith, Ralph C., Hite, Jason, Mattingly, John, Azmy, Yousry, Rajan, Deepak, Goldhahn, Ryan

Journal:

Statistical Analysis and Data Mining

Year:

2019

Language:

english

File:

PDF, 1.35 MB

english, 2019

11

neutron transport

Hart, Nathan H., Azmy, Yousry Y., Duo, Jose I.

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 10.09 MB

english, 2020

12

Dort solutions to the two-dimensional C5G7MOXbenchmark problem

Yousry Y. Azmy, Jess C. Gehin, Roberto Orsi

Journal:

Progress in Nuclear Energy

Year:

2004

Language:

english

File:

PDF, 2.01 MB

english, 2004

13

TORT solutions for the 3D radiation transport benchmarks for simple geometries with void region

Yousry Y. Azmy, Franz X. Gallmeier, Dick A. Lillie

Journal:

Progress in Nuclear Energy

Year:

2001

Language:

english

File:

PDF, 579 KB

english, 2001

14

Multiprocessing for neutron diffusion and deterministic transport methods

Journal:

Progress in Nuclear Energy

Year:

1997

Language:

english

File:

PDF, 4.05 MB

english, 1997

15

Nuclear Computational Science ||

Azmy, Yousry, Sartori, Enrico

Year:

2010

Language:

english

File:

PDF, 280 KB

english, 2010

16

Nuclear Computational Science || Nuclear Reactor Kinetics: 1934–1999 and Beyond

Azmy, Yousry, Sartori, Enrico

Year:

2010

Language:

english

File:

PDF, 1.13 MB

english, 2010

17

Nuclear Computational Science || Advances in Discrete-Ordinates Methodology

Azmy, Yousry, Sartori, Enrico

Year:

2010

Language:

english

File:

PDF, 807 KB

english, 2010

18

SPIE Proceedings [SPIE Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry - Crete, Greece (Sunday 9 June 1996)] International Conference Neutrons in Research and Industry - Recent advances in neutral particle transport methods and codes

Azmy, Yousry Y., Vourvopoulos, George

Year:

1997

Language:

english

File:

PDF, 700 KB

english, 1997

19

Newton's Method for Solving k-Eigenvalue Problems in Neutron Diffusion Theory

Gill, Daniel F., Azmy, Yousry

Journal:

Nuclear Science and Engineering

Year:

2011

Language:

english

File:

PDF, 755 KB

english, 2011

20

A Robust Arbitrarily High-Order Transport Method of the Characteristic Type for Unstructured Grids

Ferrer, Rodolfo, Azmy, Yousry

Journal:

Nuclear Science and Engineering

Year:

2012

Language:

english

File:

PDF, 813 KB

english, 2012

21

Using the Cartesian Discrete Ordinates Code DORT for Assembly-Level Calculations

Schunert, Sebastian, Azmy, Yousry

Journal:

Nuclear Science and Engineering

Year:

2013

Language:

english

File:

PDF, 2.34 MB

english, 2013

22

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

Schunert, Sebastian, Azmy, Yousry

Journal:

Nuclear Science and Engineering

Year:

2015

Language:

english

File:

PDF, 2.74 MB

english, 2015

23

Numerical convergence and validation of the DIMP inverse particle transport model

Nelson, Noel, Azmy, Yousry

Journal:

Nuclear Engineering and Technology

Year:

2017

Language:

english

File:

PDF, 1.45 MB

english, 2017

24

An Iterative Algorithm for Solving the Multidimensional Neutron Diffusion Nodal Method Equations on Parallel Computers

Kirk, Bernadette L., Azmy, Yousry Y.

Journal:

Nuclear Science and Engineering

Year:

1992

Language:

english

File:

PDF, 1013 KB

english, 1992

25

Radiation Source Mapping with Bayesian Inverse Methods

Hykes, Joshua M., Azmy, Yousry Y.

Journal:

Nuclear Science and Engineering

Year:

2015

Language:

english

File:

PDF, 1.80 MB

english, 2015

26

Properties of the S N -Equivalent Integral Transport Operator in Slab Geometry and the Iterative Acceleration of Neutral Particle Transport Methods

Rosa, Massimiliano, Azmy, Yousry Y., Morel, Jim E.

Journal:

Nuclear Science and Engineering

Year:

2009

Language:

english

File:

PDF, 554 KB

english, 2009

27

Post-Convergence Automatic Differentiation of Iterative Schemes

Azmy, Yousry Y.

Journal:

Nuclear Science and Engineering

Year:

1997

Language:

english

File:

PDF, 888 KB

english, 1997

28

On the Degradation of Cell-Centered Diffusive Preconditioners for Accelerating S N Transport Calculations in the Periodic Horizontal Interface Configuration

Rosa, Massimiliano, Azmy, Yousry Y., Morel, Jim E.

Journal:

Nuclear Science and Engineering

Year:

2010

Language:

english

File:

PDF, 437 KB

english, 2010

29

Newton’s Method for the Computation of k -Eigenvalues in S N Transport Applications

Gill, Daniel F., Azmy, Yousry Y., Warsa, James S., Densmore, Jeffery D.

Journal:

Nuclear Science and Engineering

Year:

2011

Language:

english

File:

PDF, 530 KB

english, 2011

30

Computational Modelling of Genome-Side Transcription Assembly Networks Using a Fluidics Analogy

Azmy, Yousry Y., Gupta, Anshuman, Pugh, B. Franklin, Kelso, Janet

Journal:

Year:

2008

Language:

english

File:

PDF, 215 KB

english, 2008

31

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

Hu, Xiaoyu, Azmy, Yousry Y.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 985 KB

2020