Advanced search options

Sorted by: relevance · author · university · date | New search

You searched for `subject:(Neutron transport)`

.
Showing records 1 – 30 of
165 total matches.

Search Limiters

Dates

- 2015 – 2019 (48)
- 2010 – 2014 (61)
- 2005 – 2009 (22)

Universities

- Georgia Tech (21)
- Texas A&M University (18)
- University of Michigan (18)

Department

- Nuclear Engineering (28)
- Mechanical Engineering (17)

Degrees

- PhD (56)
- MS (23)
- Docteur es (13)

▼ 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

URL: http://hdl.handle.net/1853/58184

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: https://etda.libraries.psu.edu/catalog/10162

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10394/8691

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

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

URL: http://hdl.handle.net/10019.1/19999

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: https://trace.tennessee.edu/utk_graddiss/4892

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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 Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/1969.1/155294

► 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 Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/1957/43066

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10150/347771

Subjects/Keywords: Neutron transport theory.

Record Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1969.1/173382

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10150/276711

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10919/52242

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7484

► 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 Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: https://etda.libraries.psu.edu/catalog/16160

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1969.1/165996

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10919/78127

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/10251/112422

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://rave.ohiolink.edu/etdc/view?acc_num=ucin1235764236

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1853/47612

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1853/51727

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://www.theses.fr/2016SACLS309

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/2027.42/7592

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

Record Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997

► 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 Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/1969.1/154210

► 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 Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/1957/29748

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: https://etda.libraries.psu.edu/catalog/10202

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: https://etda.libraries.psu.edu/catalog/11686

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/2027.42/6822

Subjects/Keywords: Neutron Transport Theory.; Engineering

Record Details Similar Records

❌

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

APA (6^{th} 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

Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^{th} 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.

Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^{th} 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.

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

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

URL: http://hdl.handle.net/10251/98522

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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

URL: http://hdl.handle.net/1853/59134

► 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 Details Similar Records

❌

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

APA (6^{th} 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 (16^{th} 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 (7^{th} 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