Advanced search options

Advanced Search Options 🞨

Browse by author name (“Author name starts with…”).

Find ETDs with:

in
/  
in
/  
in
/  
in

Written in Published in Earliest date Latest date

Sorted by

Results per page:

Sorted by: relevance · author · university · dateNew search

You searched for subject:(Neutron transport). Showing records 1 – 30 of 165 total matches.

[1] [2] [3] [4] [5] [6]

Search Limiters

Last 2 Years | English Only

Degrees

Levels

Country

▼ Search Limiters


Georgia Tech

1. Hon, Ryan Paul. Development of methods and tools for on-the-fly response function generation for criticality calculations.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has been developed and optimized for the computation of response functions for… (more)

Subjects/Keywords: Neutron transport

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Hon, R. P. (2016). Development of methods and tools for on-the-fly response function generation for criticality calculations. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58184

Chicago Manual of Style (16th Edition):

Hon, Ryan Paul. “Development of methods and tools for on-the-fly response function generation for criticality calculations.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/58184.

MLA Handbook (7th Edition):

Hon, Ryan Paul. “Development of methods and tools for on-the-fly response function generation for criticality calculations.” 2016. Web. 22 Apr 2019.

Vancouver:

Hon RP. Development of methods and tools for on-the-fly response function generation for criticality calculations. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/58184.

Council of Science Editors:

Hon RP. Development of methods and tools for on-the-fly response function generation for criticality calculations. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/58184


Penn State University

2. Gill, Daniel Fury. Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations.

Degree: PhD, Nuclear Engineering, 2009, Penn State University

 In this work we propose using Newton's method, specifically the inexact Newton-GMRES formulation, to solve the k-eigenvalue problem in both transport and diffusion neutronics problems.… (more)

Subjects/Keywords: JFNK; Criticality; Neutron transport; eigenvalue

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Gill, D. F. (2009). Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10162

Chicago Manual of Style (16th Edition):

Gill, Daniel Fury. “Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations.” 2009. Doctoral Dissertation, Penn State University. Accessed April 22, 2019. https://etda.libraries.psu.edu/catalog/10162.

MLA Handbook (7th Edition):

Gill, Daniel Fury. “Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations.” 2009. Web. 22 Apr 2019.

Vancouver:

Gill DF. Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations. [Internet] [Doctoral dissertation]. Penn State University; 2009. [cited 2019 Apr 22]. Available from: https://etda.libraries.psu.edu/catalog/10162.

Council of Science Editors:

Gill DF. Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations. [Doctoral Dissertation]. Penn State University; 2009. Available from: https://etda.libraries.psu.edu/catalog/10162


North-West University

3. Erasmus, Bernard. The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus .

Degree: 2012, North-West University

 In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigated. The transport model used, is derived from the Boltzmann equation… (more)

Subjects/Keywords: Lattice Boltzmann; Neutron transport

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Erasmus, B. (2012). The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus . (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/8691

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Erasmus, Bernard. “The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus .” 2012. Thesis, North-West University. Accessed April 22, 2019. http://hdl.handle.net/10394/8691.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Erasmus, Bernard. “The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus .” 2012. Web. 22 Apr 2019.

Vancouver:

Erasmus B. The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus . [Internet] [Thesis]. North-West University; 2012. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10394/8691.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Erasmus B. The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus . [Thesis]. North-West University; 2012. Available from: http://hdl.handle.net/10394/8691

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Stellenbosch University

4. Singo, Thifhelimbilu Daphney. Development of a high flux neutron radiation detection system for in-core temperature monitoring.

Degree: PhD, Physics, 2012, Stellenbosch University

 ENGLISH ABSTRACT: The objective of this research was to develop a neutron detection system that incorporates a mass spectrometer to measure high neutron flux in… (more)

Subjects/Keywords: Physics; Neutron physics; Neutron transport; High flux neutron detection systems

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Singo, T. D. (2012). Development of a high flux neutron radiation detection system for in-core temperature monitoring. (Doctoral Dissertation). Stellenbosch University. Retrieved from http://hdl.handle.net/10019.1/19999

Chicago Manual of Style (16th Edition):

Singo, Thifhelimbilu Daphney. “Development of a high flux neutron radiation detection system for in-core temperature monitoring.” 2012. Doctoral Dissertation, Stellenbosch University. Accessed April 22, 2019. http://hdl.handle.net/10019.1/19999.

MLA Handbook (7th Edition):

Singo, Thifhelimbilu Daphney. “Development of a high flux neutron radiation detection system for in-core temperature monitoring.” 2012. Web. 22 Apr 2019.

Vancouver:

Singo TD. Development of a high flux neutron radiation detection system for in-core temperature monitoring. [Internet] [Doctoral dissertation]. Stellenbosch University; 2012. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10019.1/19999.

Council of Science Editors:

Singo TD. Development of a high flux neutron radiation detection system for in-core temperature monitoring. [Doctoral Dissertation]. Stellenbosch University; 2012. Available from: http://hdl.handle.net/10019.1/19999


University of Tennessee – Knoxville

5. Hamm, Daniel Shane. Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications.

Degree: 2018, University of Tennessee – Knoxville

 Lithium indium diselenide [LISe] is under development as a single crystal semiconductor detector for neutron detection applications. Enriched in lithium-6, a neutron sensitive isotope, this… (more)

Subjects/Keywords: neutron detection; neutron radiography; 6LiInSe2; semiconductor radiation detector; charge carrier transport

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Hamm, D. S. (2018). Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/4892

Chicago Manual of Style (16th Edition):

Hamm, Daniel Shane. “Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications.” 2018. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed April 22, 2019. https://trace.tennessee.edu/utk_graddiss/4892.

MLA Handbook (7th Edition):

Hamm, Daniel Shane. “Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications.” 2018. Web. 22 Apr 2019.

Vancouver:

Hamm DS. Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2018. [cited 2019 Apr 22]. Available from: https://trace.tennessee.edu/utk_graddiss/4892.

Council of Science Editors:

Hamm DS. Development and Characterization of Lithium Indium Diselenide for Neutron Detection and Imaging Applications. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2018. Available from: https://trace.tennessee.edu/utk_graddiss/4892

6. Martin, Daniel. Modeling of boundary conditions in embedded lattice calculations.

Degree: 2015, Chalmers University of Technology

 The coupling of the fine-mesh high-order transport operator with a coarse-mesh low-order approximation, in order to reduce the computational requirements when simulating whole reactor cores,… (more)

Subjects/Keywords: neutron transport; lattice calculations; verification; validation

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Martin, D. (2015). Modeling of boundary conditions in embedded lattice calculations. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/212132-modeling-of-boundary-conditions-in-embedded-lattice-calculations

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Martin, Daniel. “Modeling of boundary conditions in embedded lattice calculations.” 2015. Thesis, Chalmers University of Technology. Accessed April 22, 2019. http://studentarbeten.chalmers.se/publication/212132-modeling-of-boundary-conditions-in-embedded-lattice-calculations.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Martin, Daniel. “Modeling of boundary conditions in embedded lattice calculations.” 2015. Web. 22 Apr 2019.

Vancouver:

Martin D. Modeling of boundary conditions in embedded lattice calculations. [Internet] [Thesis]. Chalmers University of Technology; 2015. [cited 2019 Apr 22]. Available from: http://studentarbeten.chalmers.se/publication/212132-modeling-of-boundary-conditions-in-embedded-lattice-calculations.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Martin D. Modeling of boundary conditions in embedded lattice calculations. [Thesis]. Chalmers University of Technology; 2015. Available from: http://studentarbeten.chalmers.se/publication/212132-modeling-of-boundary-conditions-in-embedded-lattice-calculations

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

7. Reed, Michael Shane. A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry.

Degree: 2015, Texas A&M University

 In this dissertation we detail the development, implementation, and testing of a new cut-cell discretization for the discrete ordinates form of the neutron transport equation.… (more)

Subjects/Keywords: Neutron Transport; cut-cell, discrete ordinates

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Reed, M. S. (2015). A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155294

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Reed, Michael Shane. “A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry.” 2015. Thesis, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/155294.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Reed, Michael Shane. “A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry.” 2015. Web. 22 Apr 2019.

Vancouver:

Reed MS. A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/155294.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Reed MS. A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry. [Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155294

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Oregon State University

8. Sterbentz, James W. An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method.

Degree: PhD, Nuclear Engineering, 1982, Oregon State University

 Spatial flux profiles were calculated in idealized, optically-thin ( 1 mfp) cell systems using integral transport theory. Numerical accuracy improvement and convergence efficiency in computing… (more)

Subjects/Keywords: Neutron transport theory

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Sterbentz, J. W. (1982). An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/43066

Chicago Manual of Style (16th Edition):

Sterbentz, James W. “An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method.” 1982. Doctoral Dissertation, Oregon State University. Accessed April 22, 2019. http://hdl.handle.net/1957/43066.

MLA Handbook (7th Edition):

Sterbentz, James W. “An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method.” 1982. Web. 22 Apr 2019.

Vancouver:

Sterbentz JW. An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method. [Internet] [Doctoral dissertation]. Oregon State University; 1982. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1957/43066.

Council of Science Editors:

Sterbentz JW. An integral transport theory boundary condition applied to close-packed lattice cells with investigations into a heuristic flux convergence method. [Doctoral Dissertation]. Oregon State University; 1982. Available from: http://hdl.handle.net/1957/43066


University of Arizona

9. Carmack, Charles William, 1947-. Flux map and reactivity measurements in the TRIGA Mark 1 reactor .

Degree: 1971, University of Arizona

Subjects/Keywords: Neutron transport theory.

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Carmack, Charles William, 1. (1971). Flux map and reactivity measurements in the TRIGA Mark 1 reactor . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/347771

Chicago Manual of Style (16th Edition):

Carmack, Charles William, 1947-. “Flux map and reactivity measurements in the TRIGA Mark 1 reactor .” 1971. Masters Thesis, University of Arizona. Accessed April 22, 2019. http://hdl.handle.net/10150/347771.

MLA Handbook (7th Edition):

Carmack, Charles William, 1947-. “Flux map and reactivity measurements in the TRIGA Mark 1 reactor .” 1971. Web. 22 Apr 2019.

Vancouver:

Carmack, Charles William 1. Flux map and reactivity measurements in the TRIGA Mark 1 reactor . [Internet] [Masters thesis]. University of Arizona; 1971. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10150/347771.

Council of Science Editors:

Carmack, Charles William 1. Flux map and reactivity measurements in the TRIGA Mark 1 reactor . [Masters Thesis]. University of Arizona; 1971. Available from: http://hdl.handle.net/10150/347771


Texas A&M University

10. Kliewer, John David. Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration.

Degree: MS, Nuclear Engineering, 2018, Texas A&M University

 A nonlinear spatial multigrid algorithm was developed and explored as a technique to efficiently solve the nonlinear S2 acceleration equations for SN neutron transport calculations… (more)

Subjects/Keywords: neutron transport; spatial multigrid; SN; S2; acceleration

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Kliewer, J. D. (2018). Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173382

Chicago Manual of Style (16th Edition):

Kliewer, John David. “Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration.” 2018. Masters Thesis, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/173382.

MLA Handbook (7th Edition):

Kliewer, John David. “Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration.” 2018. Web. 22 Apr 2019.

Vancouver:

Kliewer JD. Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/173382.

Council of Science Editors:

Kliewer JD. Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173382


University of Arizona

11. Baker, Randal Scott, 1960-. A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium .

Degree: 1988, University of Arizona

 The one-dimensional energy dependent linear neutron transport equation has been solved for the case of constant cross sections in an infinite absorbing medium with the… (more)

Subjects/Keywords: Neutron transport theory.

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Baker, Randal Scott, 1. (1988). A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/276711

Chicago Manual of Style (16th Edition):

Baker, Randal Scott, 1960-. “A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium .” 1988. Masters Thesis, University of Arizona. Accessed April 22, 2019. http://hdl.handle.net/10150/276711.

MLA Handbook (7th Edition):

Baker, Randal Scott, 1960-. “A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium .” 1988. Web. 22 Apr 2019.

Vancouver:

Baker, Randal Scott 1. A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium . [Internet] [Masters thesis]. University of Arizona; 1988. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10150/276711.

Council of Science Editors:

Baker, Randal Scott 1. A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite medium . [Masters Thesis]. University of Arizona; 1988. Available from: http://hdl.handle.net/10150/276711


Virginia Tech

12. Walters, William Jonathan. Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport.

Degree: PhD, Nuclear Engineering, 2015, Virginia Tech

 A novel collision source method has been developed to solve the Linear Boltzmann Equation (LBE) more efficiently by adaptation of the angular quadrature order. The… (more)

Subjects/Keywords: neutron transport theory; discrete ordinates; angular quadrature

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Walters, W. J. (2015). Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/52242

Chicago Manual of Style (16th Edition):

Walters, William Jonathan. “Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport.” 2015. Doctoral Dissertation, Virginia Tech. Accessed April 22, 2019. http://hdl.handle.net/10919/52242.

MLA Handbook (7th Edition):

Walters, William Jonathan. “Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport.” 2015. Web. 22 Apr 2019.

Vancouver:

Walters WJ. Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport. [Internet] [Doctoral dissertation]. Virginia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10919/52242.

Council of Science Editors:

Walters WJ. Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport. [Doctoral Dissertation]. Virginia Tech; 2015. Available from: http://hdl.handle.net/10919/52242


Texas A&M University

13. Pandya, Tara M. Long Characteristic Method in Space and Time for Transport Problems.

Degree: 2010, Texas A&M University

 Discretization and solving of the transport equation has been an area of great research where many methods have been developed. Under the deterministic transport methods,… (more)

Subjects/Keywords: method of characteristics; neutron transport; transport discretization; long characteristics

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Pandya, T. M. (2010). Long Characteristic Method in Space and Time for Transport Problems. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7484

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Pandya, Tara M. “Long Characteristic Method in Space and Time for Transport Problems.” 2010. Thesis, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7484.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Pandya, Tara M. “Long Characteristic Method in Space and Time for Transport Problems.” 2010. Web. 22 Apr 2019.

Vancouver:

Pandya TM. Long Characteristic Method in Space and Time for Transport Problems. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7484.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Pandya TM. Long Characteristic Method in Space and Time for Transport Problems. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7484

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Penn State University

14. Karriem, Zainuddin. Development of the Method of Characteristics for Embedded Lattice Physics Calculations.

Degree: PhD, Nuclear Engineering, 2012, Penn State University

 Present day reactor calculation schemes are based on a multistage approach, which involves the pregeneration of nuclear data. A fundamental step in this process is… (more)

Subjects/Keywords: Neutron Transport; Method of Characteristics; HELIOS; Emebedded Lattice Calculation; Hybrid Transport

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Karriem, Z. (2012). Development of the Method of Characteristics for Embedded Lattice Physics Calculations. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/16160

Chicago Manual of Style (16th Edition):

Karriem, Zainuddin. “Development of the Method of Characteristics for Embedded Lattice Physics Calculations.” 2012. Doctoral Dissertation, Penn State University. Accessed April 22, 2019. https://etda.libraries.psu.edu/catalog/16160.

MLA Handbook (7th Edition):

Karriem, Zainuddin. “Development of the Method of Characteristics for Embedded Lattice Physics Calculations.” 2012. Web. 22 Apr 2019.

Vancouver:

Karriem Z. Development of the Method of Characteristics for Embedded Lattice Physics Calculations. [Internet] [Doctoral dissertation]. Penn State University; 2012. [cited 2019 Apr 22]. Available from: https://etda.libraries.psu.edu/catalog/16160.

Council of Science Editors:

Karriem Z. Development of the Method of Characteristics for Embedded Lattice Physics Calculations. [Doctoral Dissertation]. Penn State University; 2012. Available from: https://etda.libraries.psu.edu/catalog/16160


Texas A&M University

15. Hammer, Hans R?diger. Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation.

Degree: PhD, Nuclear Engineering, 2017, Texas A&M University

 In this dissertation we present advances to the nonlinear diffusion acceleration for void regions using second order forms of the transport equation. We consider the… (more)

Subjects/Keywords: Neutron Transport; Nonlinear Diffusion Acceleration; Least-Squares Transport Equation

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Hammer, H. R. (2017). Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/165996

Chicago Manual of Style (16th Edition):

Hammer, Hans R?diger. “Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation.” 2017. Doctoral Dissertation, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/165996.

MLA Handbook (7th Edition):

Hammer, Hans R?diger. “Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation.” 2017. Web. 22 Apr 2019.

Vancouver:

Hammer HR. Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation. [Internet] [Doctoral dissertation]. Texas A&M University; 2017. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/165996.

Council of Science Editors:

Hammer HR. Nonlinear Diffusion Acceleration in Voids for the Least-Squares Transport Equation. [Doctoral Dissertation]. Texas A&M University; 2017. Available from: http://hdl.handle.net/1969.1/165996


Virginia Tech

16. Roskoff, Nathan J. Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code.

Degree: MS, Mechanical Engineering, 2014, Virginia Tech

 The subgroup decomposition method (SDM) has recently been developed as an improvement over the consistent generalized energy condensation theory for treatment of the energy variable… (more)

Subjects/Keywords: energy condensation; subgroup decomposition method; multigroup transport; neutron transport theory

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Roskoff, N. J. (2014). Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code. (Masters Thesis). Virginia Tech. Retrieved from http://hdl.handle.net/10919/78127

Chicago Manual of Style (16th Edition):

Roskoff, Nathan J. “Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code.” 2014. Masters Thesis, Virginia Tech. Accessed April 22, 2019. http://hdl.handle.net/10919/78127.

MLA Handbook (7th Edition):

Roskoff, Nathan J. “Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code.” 2014. Web. 22 Apr 2019.

Vancouver:

Roskoff NJ. Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code. [Internet] [Masters thesis]. Virginia Tech; 2014. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10919/78127.

Council of Science Editors:

Roskoff NJ. Implementation and Verification of the Subgroup Decomposition Method in the TITAN 3-D Deterministic Radiation Transport Code. [Masters Thesis]. Virginia Tech; 2014. Available from: http://hdl.handle.net/10919/78127


Universitat Politècnica de València

17. Bernal García, Álvaro. Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses .

Degree: 2018, Universitat Politècnica de València

 El principal objetivo de esta tesis es el desarrollo de un Método Modal para resolver dos ecuaciones: la Ecuación de la Difusión de Neutrones y… (more)

Subjects/Keywords: neutron diffusion equation; neutron transport equation; finite volume method; modal method; discrete ordinates

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Bernal García, . (2018). Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses . (Doctoral Dissertation). Universitat Politècnica de València. Retrieved from http://hdl.handle.net/10251/112422

Chicago Manual of Style (16th Edition):

Bernal García, Álvaro. “Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses .” 2018. Doctoral Dissertation, Universitat Politècnica de València. Accessed April 22, 2019. http://hdl.handle.net/10251/112422.

MLA Handbook (7th Edition):

Bernal García, Álvaro. “Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses .” 2018. Web. 22 Apr 2019.

Vancouver:

Bernal García . Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses . [Internet] [Doctoral dissertation]. Universitat Politècnica de València; 2018. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10251/112422.

Council of Science Editors:

Bernal García . Development of a 3D Modal Neutron Code with the Finite Volume Method for the Diffusion and Discrete Ordinates Transport Equations. Application to Nuclear Safety Analyses . [Doctoral Dissertation]. Universitat Politècnica de València; 2018. Available from: http://hdl.handle.net/10251/112422


University of Cincinnati

18. Taulbee, Timothy Dale. Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment.

Degree: PhD, Engineering : Nuclear and Radiological Engineering, 2009, University of Cincinnati

  The goal of this research was to determine whether neutron dose reconstruction could be improved through re-analysis of historic NTA films worn by workers… (more)

Subjects/Keywords: Radiation; NTA; proton-recoil; neutron spectroscopy; dose assessment; track length; Monte Carlo; neutron transport; neutron interactions

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Taulbee, T. D. (2009). Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment. (Doctoral Dissertation). University of Cincinnati. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=ucin1235764236

Chicago Manual of Style (16th Edition):

Taulbee, Timothy Dale. “Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment.” 2009. Doctoral Dissertation, University of Cincinnati. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1235764236.

MLA Handbook (7th Edition):

Taulbee, Timothy Dale. “Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment.” 2009. Web. 22 Apr 2019.

Vancouver:

Taulbee TD. Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment. [Internet] [Doctoral dissertation]. University of Cincinnati; 2009. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ucin1235764236.

Council of Science Editors:

Taulbee TD. Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment. [Doctoral Dissertation]. University of Cincinnati; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ucin1235764236


Georgia Tech

19. Douglass, Steven James. Consistent energy treatment for radiation transport methods.

Degree: PhD, Nuclear Engineering, 2012, Georgia Tech

 A condensed multigroup formulation is developed which maintains direct consistency with the continuous energy or fine-group structure, exhibiting the accuracy of the detailed energy spectrum… (more)

Subjects/Keywords: Neutron transport theory; Subgroup decomposition; Cross section condensation; Consistent multigroup method; Radiative transfer; Transport theory

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Douglass, S. J. (2012). Consistent energy treatment for radiation transport methods. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/47612

Chicago Manual of Style (16th Edition):

Douglass, Steven James. “Consistent energy treatment for radiation transport methods.” 2012. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/47612.

MLA Handbook (7th Edition):

Douglass, Steven James. “Consistent energy treatment for radiation transport methods.” 2012. Web. 22 Apr 2019.

Vancouver:

Douglass SJ. Consistent energy treatment for radiation transport methods. [Internet] [Doctoral dissertation]. Georgia Tech; 2012. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/47612.

Council of Science Editors:

Douglass SJ. Consistent energy treatment for radiation transport methods. [Doctoral Dissertation]. Georgia Tech; 2012. Available from: http://hdl.handle.net/1853/47612


Georgia Tech

20. Yasseri, Saam. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.

Degree: PhD, Nuclear and Radiological Engineering, 2013, Georgia Tech

 In this dissertation, three different methods for solving the Boltzmann neutron transport equation (and its low-order approximations) are developed in general geometry and implemented in… (more)

Subjects/Keywords: High-order diffusion theory; Transport spatial homogenization; Energy condensation; Neutron transport theory; Diffusion

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Yasseri, S. (2013). Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/51727

Chicago Manual of Style (16th Edition):

Yasseri, Saam. “Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.” 2013. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/51727.

MLA Handbook (7th Edition):

Yasseri, Saam. “Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.” 2013. Web. 22 Apr 2019.

Vancouver:

Yasseri S. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. [Internet] [Doctoral dissertation]. Georgia Tech; 2013. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/51727.

Council of Science Editors:

Yasseri S. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. [Doctoral Dissertation]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/51727

21. Dugan, Kevin. Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces.

Degree: Docteur es, Énergie nucléaire, 2016, Paris Saclay

 Le couplage multiphysique devient important dans les domaines de l’ingénierie nucléaire et de l’informatique. La capacité d’obtenir des solutions précises pour des modèles réalistes est… (more)

Subjects/Keywords: Multi-Physique; Homogénéisation; Transport des neutrons; Thermo-Hydraulique; Multiphysics; Homogenization; Neutron transport; Thermo-Hydraulics

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Dugan, K. (2016). Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces. (Doctoral Dissertation). Paris Saclay. Retrieved from http://www.theses.fr/2016SACLS309

Chicago Manual of Style (16th Edition):

Dugan, Kevin. “Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces.” 2016. Doctoral Dissertation, Paris Saclay. Accessed April 22, 2019. http://www.theses.fr/2016SACLS309.

MLA Handbook (7th Edition):

Dugan, Kevin. “Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces.” 2016. Web. 22 Apr 2019.

Vancouver:

Dugan K. Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces. [Internet] [Doctoral dissertation]. Paris Saclay; 2016. [cited 2019 Apr 22]. Available from: http://www.theses.fr/2016SACLS309.

Council of Science Editors:

Dugan K. Developing a Multiphysics Solver in APOLLO3 and Applications to Cross Section Homogenization : Développement d'un solveur multiphysique dans le code APOLLO3 et applications à l'homogénéisation des sections efficaces. [Doctoral Dissertation]. Paris Saclay; 2016. Available from: http://www.theses.fr/2016SACLS309


University of Michigan

22. Shultis, John Kenneth. Half-space multigroup transport theory in plane geometry : technical report.

Degree: 1968, University of Michigan

Subjects/Keywords: Neutron Transport Theory.; Transport Theory.; Engineering

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Shultis, J. K. (1968). Half-space multigroup transport theory in plane geometry : technical report. (Thesis). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/7592

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Shultis, John Kenneth. “Half-space multigroup transport theory in plane geometry : technical report.” 1968. Thesis, University of Michigan. Accessed April 22, 2019. http://hdl.handle.net/2027.42/7592.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Shultis, John Kenneth. “Half-space multigroup transport theory in plane geometry : technical report.” 1968. Web. 22 Apr 2019.

Vancouver:

Shultis JK. Half-space multigroup transport theory in plane geometry : technical report. [Internet] [Thesis]. University of Michigan; 1968. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/2027.42/7592.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Shultis JK. Half-space multigroup transport theory in plane geometry : technical report. [Thesis]. University of Michigan; 1968. Available from: http://hdl.handle.net/2027.42/7592

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

23. Wu, Zeyun. Advances in Inverse Transport Methods and Applications to Neutron Tomography.

Degree: 2011, Texas A&M University

 The purpose of the inverse-transport problems that we address is to reconstruct the material distribution inside an unknown object undergoing a nondestructive evaluation. We assume… (more)

Subjects/Keywords: Inverse transport; Neutron tomography; Conjugate gradient optimization; Heuristic optimization

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Wu, Z. (2011). Advances in Inverse Transport Methods and Applications to Neutron Tomography. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Wu, Zeyun. “Advances in Inverse Transport Methods and Applications to Neutron Tomography.” 2011. Thesis, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Wu, Zeyun. “Advances in Inverse Transport Methods and Applications to Neutron Tomography.” 2011. Web. 22 Apr 2019.

Vancouver:

Wu Z. Advances in Inverse Transport Methods and Applications to Neutron Tomography. [Internet] [Thesis]. Texas A&M University; 2011. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wu Z. Advances in Inverse Transport Methods and Applications to Neutron Tomography. [Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

24. Johns, Jesse Merlin. Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations.

Degree: 2014, Texas A&M University

 The Monte Carlo method for solving reactor physics problems is one of the most robust numerical techniques for analyzing a wide variety of systems in… (more)

Subjects/Keywords: Monte Carlo; neutron transport; nuclear depletion; temporal convergence

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Johns, J. M. (2014). Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/154210

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Johns, Jesse Merlin. “Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations.” 2014. Thesis, Texas A&M University. Accessed April 22, 2019. http://hdl.handle.net/1969.1/154210.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Johns, Jesse Merlin. “Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations.” 2014. Web. 22 Apr 2019.

Vancouver:

Johns JM. Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations. [Internet] [Thesis]. Texas A&M University; 2014. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1969.1/154210.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Johns JM. Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations. [Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/154210

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Oregon State University

25. Davis, Ian M. (Ian Mack). Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups.

Degree: MS, Nuclear Engineering, 2005, Oregon State University

 Benchmark calculations are performed for neutron transport in a two material (binary) stochastic multiplying medium. Spatial, angular, and energy dependence are included. The problem considered… (more)

Subjects/Keywords: Neutron transport theory  – Mathematical models

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Davis, I. M. (. M. (2005). Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/29748

Chicago Manual of Style (16th Edition):

Davis, Ian M (Ian Mack). “Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups.” 2005. Masters Thesis, Oregon State University. Accessed April 22, 2019. http://hdl.handle.net/1957/29748.

MLA Handbook (7th Edition):

Davis, Ian M (Ian Mack). “Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups.” 2005. Web. 22 Apr 2019.

Vancouver:

Davis IM(M. Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups. [Internet] [Masters thesis]. Oregon State University; 2005. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1957/29748.

Council of Science Editors:

Davis IM(M. Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups. [Masters Thesis]. Oregon State University; 2005. Available from: http://hdl.handle.net/1957/29748


Penn State University

26. Nelson, Adam Gregory. MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA.

Degree: MS, Nuclear Engineering, 2009, Penn State University

 This work examined the feasibility of utilizing Graphics Processing Units (GPUs) to accelerate Monte Carlo neutron transport problems. These GPUs use many parallel processors to… (more)

Subjects/Keywords: gpu; neutron transport; gp-gpu; monte carlo; cuda

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Nelson, A. G. (2009). MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10202

Chicago Manual of Style (16th Edition):

Nelson, Adam Gregory. “MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA.” 2009. Masters Thesis, Penn State University. Accessed April 22, 2019. https://etda.libraries.psu.edu/catalog/10202.

MLA Handbook (7th Edition):

Nelson, Adam Gregory. “MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA.” 2009. Web. 22 Apr 2019.

Vancouver:

Nelson AG. MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA. [Internet] [Masters thesis]. Penn State University; 2009. [cited 2019 Apr 22]. Available from: https://etda.libraries.psu.edu/catalog/10202.

Council of Science Editors:

Nelson AG. MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA. [Masters Thesis]. Penn State University; 2009. Available from: https://etda.libraries.psu.edu/catalog/10202


Penn State University

27. Zerr, Robert Joseph. Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures.

Degree: PhD, Nuclear Engineering, 2011, Penn State University

 The integral transport matrix method (ITMM) has been used as the kernel of new parallel solution methods for the discrete ordinates approximation of the within-group… (more)

Subjects/Keywords: neutron transport; discrete ordinates; within-group; massively parallel; spatial domain decomposition

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Zerr, R. J. (2011). Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/11686

Chicago Manual of Style (16th Edition):

Zerr, Robert Joseph. “Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures.” 2011. Doctoral Dissertation, Penn State University. Accessed April 22, 2019. https://etda.libraries.psu.edu/catalog/11686.

MLA Handbook (7th Edition):

Zerr, Robert Joseph. “Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures.” 2011. Web. 22 Apr 2019.

Vancouver:

Zerr RJ. Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures. [Internet] [Doctoral dissertation]. Penn State University; 2011. [cited 2019 Apr 22]. Available from: https://etda.libraries.psu.edu/catalog/11686.

Council of Science Editors:

Zerr RJ. Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures. [Doctoral Dissertation]. Penn State University; 2011. Available from: https://etda.libraries.psu.edu/catalog/11686


University of Michigan

28. Zweifel, P. F. (Paul Frederick). Energy-dependent neutron transport theory in the fast domain : technical report.

Degree: 1968, University of Michigan

Subjects/Keywords: Neutron Transport Theory.; Engineering

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Zweifel, P. F. (. F. (1968). Energy-dependent neutron transport theory in the fast domain : technical report. (Thesis). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/6822

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Zweifel, P F (Paul Frederick). “Energy-dependent neutron transport theory in the fast domain : technical report.” 1968. Thesis, University of Michigan. Accessed April 22, 2019. http://hdl.handle.net/2027.42/6822.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Zweifel, P F (Paul Frederick). “Energy-dependent neutron transport theory in the fast domain : technical report.” 1968. Web. 22 Apr 2019.

Vancouver:

Zweifel PF(F. Energy-dependent neutron transport theory in the fast domain : technical report. [Internet] [Thesis]. University of Michigan; 1968. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/2027.42/6822.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Zweifel PF(F. Energy-dependent neutron transport theory in the fast domain : technical report. [Thesis]. University of Michigan; 1968. Available from: http://hdl.handle.net/2027.42/6822

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Universitat Politècnica de València

29. Vidal Ferràndiz, Antoni. Development of a finite element method for neutron transport equation approximations .

Degree: 2018, Universitat Politècnica de València

 La ecuación del transporte neutrónico describe la población de neutrones y las reacciones nucleares dentro de un reactor nuclear. Primero, introducimos esta ecuación y las… (more)

Subjects/Keywords: Finite element method; neutron transport equation; nuclear engineering

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Vidal Ferràndiz, A. (2018). Development of a finite element method for neutron transport equation approximations . (Doctoral Dissertation). Universitat Politècnica de València. Retrieved from http://hdl.handle.net/10251/98522

Chicago Manual of Style (16th Edition):

Vidal Ferràndiz, Antoni. “Development of a finite element method for neutron transport equation approximations .” 2018. Doctoral Dissertation, Universitat Politècnica de València. Accessed April 22, 2019. http://hdl.handle.net/10251/98522.

MLA Handbook (7th Edition):

Vidal Ferràndiz, Antoni. “Development of a finite element method for neutron transport equation approximations .” 2018. Web. 22 Apr 2019.

Vancouver:

Vidal Ferràndiz A. Development of a finite element method for neutron transport equation approximations . [Internet] [Doctoral dissertation]. Universitat Politècnica de València; 2018. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/10251/98522.

Council of Science Editors:

Vidal Ferràndiz A. Development of a finite element method for neutron transport equation approximations . [Doctoral Dissertation]. Universitat Politècnica de València; 2018. Available from: http://hdl.handle.net/10251/98522


Georgia Tech

30. Kooreman, Gabriel. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The neutron transport equation often is homogenized in order to simplify its solution procedure in some manner or another. There exist many methods for homogenizing… (more)

Subjects/Keywords: Neutron transport; Homogenization; Diffusion; Eigenvalue calculation; Reactor physics

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Kooreman, G. (2016). Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59134

Chicago Manual of Style (16th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/59134.

MLA Handbook (7th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Web. 22 Apr 2019.

Vancouver:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/59134.

Council of Science Editors:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/59134

[1] [2] [3] [4] [5] [6]

.