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You searched for subject:(neutron transport). Showing records 1 – 30 of 209 total matches.

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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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


North-West University

2. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Erasmus B. The Lattice Boltzmann Method applied to linear particle transport / Bernard Erasmus . [Internet] [Thesis]. North-West University; 2012. [cited 2021 Apr 17]. 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

3. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Singo TD. Development of a high flux neutron radiation detection system for in-core temperature monitoring. [Internet] [Doctoral dissertation]. Stellenbosch University; 2012. [cited 2021 Apr 17]. 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

4. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


Oregon State University

5. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


Texas A&M University

6. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Kliewer JD. Non-Linear Spatial Multigrid Method For Non-Linear S2 Acceleration. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Apr 17]. 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


Texas A&M University

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

Degree: PhD, Nuclear Engineering, 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

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APA (6th Edition):

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

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. Doctoral Dissertation, Texas A&M University. Accessed April 17, 2021. http://hdl.handle.net/1969.1/155294.

MLA Handbook (7th Edition):

Reed, Michael Shane. “A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry.” 2015. Web. 17 Apr 2021.

Vancouver:

Reed MS. A Second Order Linear Discontinuous Cut-Cell Discretization for the SN Equations in RZ Geometry. [Internet] [Doctoral dissertation]. Texas A&M University; 2015. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/1969.1/155294.

Council of Science Editors:

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


University of Arizona

8. 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.

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


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.

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Carmack, Charles William 1. Flux map and reactivity measurements in the TRIGA Mark 1 reactor . [Internet] [Masters thesis]. University of Arizona; 1971. [cited 2021 Apr 17]. 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


Georgia Tech

10. Cobb, William Ronald. Application of variational synthesis to solutions of multidimensional neutron transport problems.

Degree: PhD, Nuclear Engineering, 1970, Georgia Tech

Subjects/Keywords: Neutron transport theory

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APA (6th Edition):

Cobb, W. R. (1970). Application of variational synthesis to solutions of multidimensional neutron transport problems. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/13373

Chicago Manual of Style (16th Edition):

Cobb, William Ronald. “Application of variational synthesis to solutions of multidimensional neutron transport problems.” 1970. Doctoral Dissertation, Georgia Tech. Accessed April 17, 2021. http://hdl.handle.net/1853/13373.

MLA Handbook (7th Edition):

Cobb, William Ronald. “Application of variational synthesis to solutions of multidimensional neutron transport problems.” 1970. Web. 17 Apr 2021.

Vancouver:

Cobb WR. Application of variational synthesis to solutions of multidimensional neutron transport problems. [Internet] [Doctoral dissertation]. Georgia Tech; 1970. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/1853/13373.

Council of Science Editors:

Cobb WR. Application of variational synthesis to solutions of multidimensional neutron transport problems. [Doctoral Dissertation]. Georgia Tech; 1970. Available from: http://hdl.handle.net/1853/13373


Virginia Tech

11. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Walters WJ. Development of the Adaptive Collision Source Method for Discrete Ordinates Radiation Transport. [Internet] [Doctoral dissertation]. Virginia Tech; 2015. [cited 2021 Apr 17]. 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


Virginia Tech

12. Butler, James Michael. Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook.

Degree: MS, Nuclear Engineering, 2019, Virginia Tech

 In the modeling and simulation of nuclear systems, two parameters are of key importance: the system eigenvalue and the fission distribution. The system eigenvalue, known… (more)

Subjects/Keywords: neutron transport theory; fission matrix; criticality safety

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APA (6th Edition):

Butler, J. M. (2019). Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook. (Masters Thesis). Virginia Tech. Retrieved from http://hdl.handle.net/10919/93745

Chicago Manual of Style (16th Edition):

Butler, James Michael. “Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook.” 2019. Masters Thesis, Virginia Tech. Accessed April 17, 2021. http://hdl.handle.net/10919/93745.

MLA Handbook (7th Edition):

Butler, James Michael. “Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook.” 2019. Web. 17 Apr 2021.

Vancouver:

Butler JM. Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook. [Internet] [Masters thesis]. Virginia Tech; 2019. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/10919/93745.

Council of Science Editors:

Butler JM. Benchmarking of the RAPID Eigenvalue Algorithm using the ICSBEP Handbook. [Masters Thesis]. Virginia Tech; 2019. Available from: http://hdl.handle.net/10919/93745


Penn State University

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

Degree: 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

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APA (6th Edition):

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

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):

Karriem, Zainuddin. “Development of the Method of Characteristics for Embedded Lattice Physics Calculations.” 2012. Thesis, Penn State University. Accessed April 17, 2021. https://submit-etda.libraries.psu.edu/catalog/16160.

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

MLA Handbook (7th Edition):

Karriem, Zainuddin. “Development of the Method of Characteristics for Embedded Lattice Physics Calculations.” 2012. Web. 17 Apr 2021.

Vancouver:

Karriem Z. Development of the Method of Characteristics for Embedded Lattice Physics Calculations. [Internet] [Thesis]. Penn State University; 2012. [cited 2021 Apr 17]. Available from: https://submit-etda.libraries.psu.edu/catalog/16160.

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

Council of Science Editors:

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

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


Virginia Tech

14. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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

15. TARDELLI, TIAGO C. Avaliação de dados nucleares para dosimetria de nêutrons.

Degree: 2013, Brazil

Made available in DSpace on 2014-10-09T12:42:16Z (GMT). No. of bitstreams: 0

Made available in DSpace on 2014-10-09T14:05:21Z (GMT). No. of bitstreams: 0

Doses absorvidas e… (more)

Subjects/Keywords: neutron transport; neutron emission; neutron sources; neutron flux; neutron dosimetry; interactions; measurement; radiation dose units; nuclear energy; data analysis; computer codes; monte carlo method

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APA (6th Edition):

TARDELLI, T. C. (2013). Avaliação de dados nucleares para dosimetria de nêutrons. (Masters Thesis). Brazil. Retrieved from http://repositorio.ipen.br:8080/xmlui/handle/123456789/10587

Chicago Manual of Style (16th Edition):

TARDELLI, TIAGO C. “Avaliação de dados nucleares para dosimetria de nêutrons.” 2013. Masters Thesis, Brazil. Accessed April 17, 2021. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10587.

MLA Handbook (7th Edition):

TARDELLI, TIAGO C. “Avaliação de dados nucleares para dosimetria de nêutrons.” 2013. Web. 17 Apr 2021.

Vancouver:

TARDELLI TC. Avaliação de dados nucleares para dosimetria de nêutrons. [Internet] [Masters thesis]. Brazil; 2013. [cited 2021 Apr 17]. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10587.

Council of Science Editors:

TARDELLI TC. Avaliação de dados nucleares para dosimetria de nêutrons. [Masters Thesis]. Brazil; 2013. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10587


Universitat Politècnica de València

16. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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

17. Wang, Yunsong. Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs.

Degree: Docteur es, Informatique, 2017, Université Paris-Saclay (ComUE)

L’accès aux données de base, que sont les sections efficaces, constitue le principal goulot d’étranglement aux performances dans la résolution des équations du transport neutronique… (more)

Subjects/Keywords: Monte Carlo; Transport de neutron; Section efficace; Mic; Vectorisation; Programmation Parallèle; Monte Carlo; Neutron transport; Cross section; Mic; Vectorization; Parallel computing

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APA (6th Edition):

Wang, Y. (2017). Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs. (Doctoral Dissertation). Université Paris-Saclay (ComUE). Retrieved from http://www.theses.fr/2017SACLX090

Chicago Manual of Style (16th Edition):

Wang, Yunsong. “Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs.” 2017. Doctoral Dissertation, Université Paris-Saclay (ComUE). Accessed April 17, 2021. http://www.theses.fr/2017SACLX090.

MLA Handbook (7th Edition):

Wang, Yunsong. “Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs.” 2017. Web. 17 Apr 2021.

Vancouver:

Wang Y. Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs. [Internet] [Doctoral dissertation]. Université Paris-Saclay (ComUE); 2017. [cited 2021 Apr 17]. Available from: http://www.theses.fr/2017SACLX090.

Council of Science Editors:

Wang Y. Optimization of Monte Carlo Neutron Transport Simulations with Emerging Architectures : Optimisation du code Monte Carlo neutronique à l’aide d’accélérateurs de calculs. [Doctoral Dissertation]. Université Paris-Saclay (ComUE); 2017. Available from: http://www.theses.fr/2017SACLX090


University of Michigan

18. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Shultis JK. Half-space multigroup transport theory in plane geometry : technical report. [Internet] [Thesis]. University of Michigan; 1968. [cited 2021 Apr 17]. 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

19. 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, Université Paris-Saclay (ComUE)

 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

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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). Université Paris-Saclay (ComUE). 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, Université Paris-Saclay (ComUE). Accessed April 17, 2021. 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. 17 Apr 2021.

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]. Université Paris-Saclay (ComUE); 2016. [cited 2021 Apr 17]. 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]. Université Paris-Saclay (ComUE); 2016. Available from: http://www.theses.fr/2016SACLS309


Georgia Tech

20. 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

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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 17, 2021. http://hdl.handle.net/1853/47612.

MLA Handbook (7th Edition):

Douglass, Steven James. “Consistent energy treatment for radiation transport methods.” 2012. Web. 17 Apr 2021.

Vancouver:

Douglass SJ. Consistent energy treatment for radiation transport methods. [Internet] [Doctoral dissertation]. Georgia Tech; 2012. [cited 2021 Apr 17]. 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

21. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


University of New Mexico

22. Wakeford, Daniel T. A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport.

Degree: Nuclear Engineering, 2020, University of New Mexico

  A natural coordinate system for calculating neutral particle propagation in the atmosphere due to point sources is two-dimensional spherical-polar coordinates. Deterministic methods for solving… (more)

Subjects/Keywords: multi-dimensional orthogonal curvilinear discontinuous method; discret ordinates; neutron transport; atmospheric transport; Nuclear Engineering

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APA (6th Edition):

Wakeford, D. T. (2020). A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport. (Doctoral Dissertation). University of New Mexico. Retrieved from https://digitalrepository.unm.edu/ne_etds/97

Chicago Manual of Style (16th Edition):

Wakeford, Daniel T. “A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport.” 2020. Doctoral Dissertation, University of New Mexico. Accessed April 17, 2021. https://digitalrepository.unm.edu/ne_etds/97.

MLA Handbook (7th Edition):

Wakeford, Daniel T. “A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport.” 2020. Web. 17 Apr 2021.

Vancouver:

Wakeford DT. A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport. [Internet] [Doctoral dissertation]. University of New Mexico; 2020. [cited 2021 Apr 17]. Available from: https://digitalrepository.unm.edu/ne_etds/97.

Council of Science Editors:

Wakeford DT. A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport. [Doctoral Dissertation]. University of New Mexico; 2020. Available from: https://digitalrepository.unm.edu/ne_etds/97


Oregon State University

23. 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

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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 17, 2021. 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. 17 Apr 2021.

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 2021 Apr 17]. 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


University of Michigan

24. Fitzgerald, Andrew. Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration.

Degree: PhD, Nuclear Engineering & Radiological Sciences, 2020, University of Michigan

 In the design and analysis of nuclear fission reactor systems, simulations are an essential tool for improving efficiency and safety. Neutronics simulations have always been… (more)

Subjects/Keywords: neutron transport; Nuclear Engineering and Radiological Sciences; Engineering

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APA (6th Edition):

Fitzgerald, A. (2020). Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration. (Doctoral Dissertation). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/155260

Chicago Manual of Style (16th Edition):

Fitzgerald, Andrew. “Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration.” 2020. Doctoral Dissertation, University of Michigan. Accessed April 17, 2021. http://hdl.handle.net/2027.42/155260.

MLA Handbook (7th Edition):

Fitzgerald, Andrew. “Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration.” 2020. Web. 17 Apr 2021.

Vancouver:

Fitzgerald A. Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration. [Internet] [Doctoral dissertation]. University of Michigan; 2020. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/2027.42/155260.

Council of Science Editors:

Fitzgerald A. Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration. [Doctoral Dissertation]. University of Michigan; 2020. Available from: http://hdl.handle.net/2027.42/155260


University of Michigan

25. 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

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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 17, 2021. 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. 17 Apr 2021.

Vancouver:

Zweifel PF(F. Energy-dependent neutron transport theory in the fast domain : technical report. [Internet] [Thesis]. University of Michigan; 1968. [cited 2021 Apr 17]. 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


Penn State University

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

Degree: 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

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APA (6th Edition):

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

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):

Gill, Daniel Fury. “Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations .” 2009. Thesis, Penn State University. Accessed April 17, 2021. https://submit-etda.libraries.psu.edu/catalog/10162.

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

MLA Handbook (7th Edition):

Gill, Daniel Fury. “Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations .” 2009. Web. 17 Apr 2021.

Vancouver:

Gill DF. Newton-Krylov Methods for the Solution of the k-Eigenvalue Problem in Multigroup Neutronics Calculations . [Internet] [Thesis]. Penn State University; 2009. [cited 2021 Apr 17]. Available from: https://submit-etda.libraries.psu.edu/catalog/10162.

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

Council of Science Editors:

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

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


Texas A&M University

27. Bruss, Donald Eugene. Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

 The accurate modeling of complex physical phenomena, such as radiation transport in a laboratory experiment or a nuclear reactor, challenges the limits of modern computing… (more)

Subjects/Keywords: Adjoint; Uncertainty Quantification; Neutron Transport; Cross Section Uncertainty; NJOY

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APA (6th Edition):

Bruss, D. E. (2016). Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158116

Chicago Manual of Style (16th Edition):

Bruss, Donald Eugene. “Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations.” 2016. Doctoral Dissertation, Texas A&M University. Accessed April 17, 2021. http://hdl.handle.net/1969.1/158116.

MLA Handbook (7th Edition):

Bruss, Donald Eugene. “Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations.” 2016. Web. 17 Apr 2021.

Vancouver:

Bruss DE. Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/1969.1/158116.

Council of Science Editors:

Bruss DE. Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/158116


Texas A&M University

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

Degree: PhD, Nuclear Engineering, 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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Wu, Zeyun. “Advances in Inverse Transport Methods and Applications to Neutron Tomography.” 2011. Doctoral Dissertation, Texas A&M University. Accessed April 17, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997.

MLA Handbook (7th Edition):

Wu, Zeyun. “Advances in Inverse Transport Methods and Applications to Neutron Tomography.” 2011. Web. 17 Apr 2021.

Vancouver:

Wu Z. Advances in Inverse Transport Methods and Applications to Neutron Tomography. [Internet] [Doctoral dissertation]. Texas A&M University; 2011. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8997.

Council of Science Editors:

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


Texas A&M University

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

Degree: PhD, Nuclear Engineering, 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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Johns, Jesse Merlin. “Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations.” 2014. Doctoral Dissertation, Texas A&M University. Accessed April 17, 2021. http://hdl.handle.net/1969.1/154210.

MLA Handbook (7th Edition):

Johns, Jesse Merlin. “Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations.” 2014. Web. 17 Apr 2021.

Vancouver:

Johns JM. Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations. [Internet] [Doctoral dissertation]. Texas A&M University; 2014. [cited 2021 Apr 17]. Available from: http://hdl.handle.net/1969.1/154210.

Council of Science Editors:

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


Penn State University

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

Degree: 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

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APA (6th Edition):

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

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):

Zerr, Robert Joseph. “Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures.” 2011. Thesis, Penn State University. Accessed April 17, 2021. https://submit-etda.libraries.psu.edu/catalog/11686.

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

MLA Handbook (7th Edition):

Zerr, Robert Joseph. “Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures.” 2011. Web. 17 Apr 2021.

Vancouver:

Zerr RJ. Solution of the Within-Group Multidimensional Discrete Ordinates Transport Equations on Massively Parallel Architectures. [Internet] [Thesis]. Penn State University; 2011. [cited 2021 Apr 17]. Available from: https://submit-etda.libraries.psu.edu/catalog/11686.

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

Council of Science Editors:

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

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

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