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You searched for +publisher:"University of New Mexico" +contributor:("Prinja, Anil"). Showing records 1 – 24 of 24 total matches.

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University of New Mexico

1. Elfrgani, Ahmed. RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES.

Degree: Electrical and Computer Engineering, 2016, University of New Mexico

 Short pulse high power microwave (HPM) devices with Gaussian radiation pattern are attractive for many applications. The importance of the Gaussian microwave beam is that… (more)

Subjects/Keywords: Relativistic Backward Wave Oscilator; Bragg Reflector; Dual Band Source; Power Combiner; Gaussian Radiation Pattern

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APA (6th Edition):

Elfrgani, A. (2016). RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/31716

Chicago Manual of Style (16th Edition):

Elfrgani, Ahmed. “RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES.” 2016. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/31716.

MLA Handbook (7th Edition):

Elfrgani, Ahmed. “RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES.” 2016. Web. 25 Jun 2019.

Vancouver:

Elfrgani A. RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES. [Internet] [Doctoral dissertation]. University of New Mexico; 2016. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/31716.

Council of Science Editors:

Elfrgani A. RELATIVISTIC BACKWARD WAVE OSCILLATOR WITH A GAUSSIAN RADIATION PATTERN AND RELATED TECHNOLOGIES. [Doctoral Dissertation]. University of New Mexico; 2016. Available from: http://hdl.handle.net/1928/31716


University of New Mexico

2. Taitano, William. Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion.

Degree: Nuclear Engineering, 2014, University of New Mexico

 In inertial confinement fusion (ICF), the kinetic ion and charge separation field effects may play a significant role in the difference between the measured neutron… (more)

Subjects/Keywords: moment based accelerator; plasma physics; inertial confinement fusion; mix; kinetic; HOLO

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APA (6th Edition):

Taitano, W. (2014). Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24349

Chicago Manual of Style (16th Edition):

Taitano, William. “Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion.” 2014. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/24349.

MLA Handbook (7th Edition):

Taitano, William. “Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion.” 2014. Web. 25 Jun 2019.

Vancouver:

Taitano W. Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion. [Internet] [Doctoral dissertation]. University of New Mexico; 2014. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/24349.

Council of Science Editors:

Taitano W. Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion. [Doctoral Dissertation]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24349


University of New Mexico

3. Myers, Nicholas. An Sn Application of Homotopy Continuation in Neutral Particle Transport.

Degree: Nuclear Engineering, 2014, University of New Mexico

 The objective of this dissertation is to investigate the usefulness of homotopy continuation applied in the context of neutral particle transport where traditional methods of… (more)

Subjects/Keywords: Homotopy; Sn; Continuation; Transport; Eigenvalue; Diffusive

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APA (6th Edition):

Myers, N. (2014). An Sn Application of Homotopy Continuation in Neutral Particle Transport. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24581

Chicago Manual of Style (16th Edition):

Myers, Nicholas. “An Sn Application of Homotopy Continuation in Neutral Particle Transport.” 2014. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/24581.

MLA Handbook (7th Edition):

Myers, Nicholas. “An Sn Application of Homotopy Continuation in Neutral Particle Transport.” 2014. Web. 25 Jun 2019.

Vancouver:

Myers N. An Sn Application of Homotopy Continuation in Neutral Particle Transport. [Internet] [Doctoral dissertation]. University of New Mexico; 2014. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/24581.

Council of Science Editors:

Myers N. An Sn Application of Homotopy Continuation in Neutral Particle Transport. [Doctoral Dissertation]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24581


University of New Mexico

4. Bowen, Douglas. Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico.

Degree: Nuclear Engineering, 2015, University of New Mexico

 A series of experimental measurements were performed on the AGN- 201M reactor (AGN) at the University of New Mexico. Steady-state measurements were made with the… (more)

Subjects/Keywords: AGN-201; Research Reactor; critical; transient; EVENT

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APA (6th Edition):

Bowen, D. (2015). Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/27762

Chicago Manual of Style (16th Edition):

Bowen, Douglas. “Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico.” 2015. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/27762.

MLA Handbook (7th Edition):

Bowen, Douglas. “Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico.” 2015. Web. 25 Jun 2019.

Vancouver:

Bowen D. Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico. [Internet] [Doctoral dissertation]. University of New Mexico; 2015. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/27762.

Council of Science Editors:

Bowen D. Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico. [Doctoral Dissertation]. University of New Mexico; 2015. Available from: http://hdl.handle.net/1928/27762


University of New Mexico

5. Nelson, Alan. A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments.

Degree: Nuclear Engineering, 2012, University of New Mexico

 There are several machines in this country that produce short bursts of neutrons for various applications. A few examples are the Z-machine, operated by Sandia… (more)

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APA (6th Edition):

Nelson, A. (2012). A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/17493

Chicago Manual of Style (16th Edition):

Nelson, Alan. “A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments.” 2012. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/17493.

MLA Handbook (7th Edition):

Nelson, Alan. “A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments.” 2012. Web. 25 Jun 2019.

Vancouver:

Nelson A. A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments. [Internet] [Doctoral dissertation]. University of New Mexico; 2012. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/17493.

Council of Science Editors:

Nelson A. A novel method for modeling the neutron Time of Flight (nTOF) detector response in current mode to inertial confinement fusion experiments. [Doctoral Dissertation]. University of New Mexico; 2012. Available from: http://hdl.handle.net/1928/17493


University of New Mexico

6. Rising, Michael. Quantification and propagation of nuclear data uncertainties.

Degree: Nuclear Engineering, 2013, University of New Mexico

 The use of several uncertainty quantification and propagation methodologies is investigated in the context of the prompt fission neutron spectrum (PFNS) uncertainties and its impact… (more)

Subjects/Keywords: Prompt neutrons – Spectra – Measurement.; Neutron transport theory.; Spontaneous fission – Data processing.; Uncertainty – Mathematical models.

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APA (6th Edition):

Rising, M. (2013). Quantification and propagation of nuclear data uncertainties. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/22068

Chicago Manual of Style (16th Edition):

Rising, Michael. “Quantification and propagation of nuclear data uncertainties.” 2013. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/22068.

MLA Handbook (7th Edition):

Rising, Michael. “Quantification and propagation of nuclear data uncertainties.” 2013. Web. 25 Jun 2019.

Vancouver:

Rising M. Quantification and propagation of nuclear data uncertainties. [Internet] [Doctoral dissertation]. University of New Mexico; 2013. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/22068.

Council of Science Editors:

Rising M. Quantification and propagation of nuclear data uncertainties. [Doctoral Dissertation]. University of New Mexico; 2013. Available from: http://hdl.handle.net/1928/22068


University of New Mexico

7. Ortega, Mario Ivan. Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations.

Degree: Nuclear Engineering, 2016, University of New Mexico

 In the solution of the neutron transport equation, the k-effective eigenvalue is related to the average number of neutrons emitted in fission of the system.… (more)

Subjects/Keywords: Monte Carlo; criticality; fission multiplicity; fission neutron energy correlation; nuclear data uncertainty

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APA (6th Edition):

Ortega, M. I. (2016). Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/31686

Chicago Manual of Style (16th Edition):

Ortega, Mario Ivan. “Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations.” 2016. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/31686.

MLA Handbook (7th Edition):

Ortega, Mario Ivan. “Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations.” 2016. Web. 25 Jun 2019.

Vancouver:

Ortega MI. Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations. [Internet] [Masters thesis]. University of New Mexico; 2016. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/31686.

Council of Science Editors:

Ortega MI. Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations. [Masters Thesis]. University of New Mexico; 2016. Available from: http://hdl.handle.net/1928/31686


University of New Mexico

8. Barber, Allison. Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis.

Degree: Nuclear Engineering, 2010, University of New Mexico

 The uncertainty of a critical benchmark experiment is a very important result. This value tells how well each parameter in the system is known and… (more)

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APA (6th Edition):

Barber, A. (2010). Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/10803

Chicago Manual of Style (16th Edition):

Barber, Allison. “Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis.” 2010. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/10803.

MLA Handbook (7th Edition):

Barber, Allison. “Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis.” 2010. Web. 25 Jun 2019.

Vancouver:

Barber A. Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis. [Internet] [Masters thesis]. University of New Mexico; 2010. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/10803.

Council of Science Editors:

Barber A. Development of sensitivity analysis with the use of TSUNAMI-3D sensitivity coefficients for benchmark uncertainty analysis. [Masters Thesis]. University of New Mexico; 2010. Available from: http://hdl.handle.net/1928/10803


University of New Mexico

9. Chapman, Bryan Scott. Diagnostics of source distribution and particle population in Monte Carlo source iteration methods.

Degree: Nuclear Engineering, 2010, University of New Mexico

 This thesis is concerned with the development of mesh-input-free diagnostics for the determination of the iteration at which the source distribution of a Monte Carlo… (more)

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APA (6th Edition):

Chapman, B. S. (2010). Diagnostics of source distribution and particle population in Monte Carlo source iteration methods. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/10808

Chicago Manual of Style (16th Edition):

Chapman, Bryan Scott. “Diagnostics of source distribution and particle population in Monte Carlo source iteration methods.” 2010. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/10808.

MLA Handbook (7th Edition):

Chapman, Bryan Scott. “Diagnostics of source distribution and particle population in Monte Carlo source iteration methods.” 2010. Web. 25 Jun 2019.

Vancouver:

Chapman BS. Diagnostics of source distribution and particle population in Monte Carlo source iteration methods. [Internet] [Masters thesis]. University of New Mexico; 2010. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/10808.

Council of Science Editors:

Chapman BS. Diagnostics of source distribution and particle population in Monte Carlo source iteration methods. [Masters Thesis]. University of New Mexico; 2010. Available from: http://hdl.handle.net/1928/10808


University of New Mexico

10. Gonzales, Matthew. A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling.

Degree: Nuclear Engineering, 2013, University of New Mexico

 Analog simulation of energy straggling of electrons and positrons is computationally impractical because of long-range Coulomb forces resulting in highly peaked cross sections about small… (more)

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APA (6th Edition):

Gonzales, M. (2013). A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/22002

Chicago Manual of Style (16th Edition):

Gonzales, Matthew. “A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling.” 2013. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/22002.

MLA Handbook (7th Edition):

Gonzales, Matthew. “A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling.” 2013. Web. 25 Jun 2019.

Vancouver:

Gonzales M. A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling. [Internet] [Masters thesis]. University of New Mexico; 2013. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/22002.

Council of Science Editors:

Gonzales M. A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling. [Masters Thesis]. University of New Mexico; 2013. Available from: http://hdl.handle.net/1928/22002


University of New Mexico

11. Kamm, Ryan J. Eigenfunction expansion of the time and space-dependent neutron survival probability equation.

Degree: Nuclear Engineering, 2013, University of New Mexico

 Owing to their inherent complexity, stochastic neutron transport problems are often examined by either using highly simplified models to make solutions more accessible, or at… (more)

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APA (6th Edition):

Kamm, R. J. (2013). Eigenfunction expansion of the time and space-dependent neutron survival probability equation. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/22006

Chicago Manual of Style (16th Edition):

Kamm, Ryan J. “Eigenfunction expansion of the time and space-dependent neutron survival probability equation.” 2013. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/22006.

MLA Handbook (7th Edition):

Kamm, Ryan J. “Eigenfunction expansion of the time and space-dependent neutron survival probability equation.” 2013. Web. 25 Jun 2019.

Vancouver:

Kamm RJ. Eigenfunction expansion of the time and space-dependent neutron survival probability equation. [Internet] [Masters thesis]. University of New Mexico; 2013. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/22006.

Council of Science Editors:

Kamm RJ. Eigenfunction expansion of the time and space-dependent neutron survival probability equation. [Masters Thesis]. University of New Mexico; 2013. Available from: http://hdl.handle.net/1928/22006


University of New Mexico

12. Patel, Japan. Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry.

Degree: Nuclear Engineering, 2014, University of New Mexico

 In this thesis, we discuss a coupling algorithm to model simplified fast burst reactor dynamics. Kadioglu presented a tightly coupled multiphysics algorithm of diffusion neutronics… (more)

Subjects/Keywords: neutron transport; nonlinear diffusion acceleration; IMplicit EXplicit; Multiphysics; Newton method; HOLO; linear mechanics; temperature equation; fast burst reactor dynamics

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APA (6th Edition):

Patel, J. (2014). Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24503

Chicago Manual of Style (16th Edition):

Patel, Japan. “Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry.” 2014. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/24503.

MLA Handbook (7th Edition):

Patel, Japan. “Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry.” 2014. Web. 25 Jun 2019.

Vancouver:

Patel J. Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry. [Internet] [Masters thesis]. University of New Mexico; 2014. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/24503.

Council of Science Editors:

Patel J. Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry. [Masters Thesis]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24503


University of New Mexico

13. Drumm, Amy. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).

Degree: Nuclear Engineering, 2015, University of New Mexico

 The purpose of this work was to develop and validate a design tool for the transients that are of interest in designing the decay heat… (more)

Subjects/Keywords: Numerical Methods; Fluoride salt-cooled High-temperature Reactor (FHR); Validation Study; Thermal Hydraulics

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APA (6th Edition):

Drumm, A. (2015). Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/25738

Chicago Manual of Style (16th Edition):

Drumm, Amy. “Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).” 2015. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/25738.

MLA Handbook (7th Edition):

Drumm, Amy. “Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).” 2015. Web. 25 Jun 2019.

Vancouver:

Drumm A. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). [Internet] [Masters thesis]. University of New Mexico; 2015. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/25738.

Council of Science Editors:

Drumm A. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). [Masters Thesis]. University of New Mexico; 2015. Available from: http://hdl.handle.net/1928/25738


University of New Mexico

14. Lafreniere, Philip. IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING.

Degree: Nuclear Engineering, 2015, University of New Mexico

 The traditional method of safeguarding nuclear facilities, nuclear material accountancy (NMA), faces many challenges when applied to pyroprocessing facilities. To aid in the safeguarding of… (more)

Subjects/Keywords: Pyroprocessing; Signature Based Safeguards; Computer Modeling

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APA (6th Edition):

Lafreniere, P. (2015). IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/25757

Chicago Manual of Style (16th Edition):

Lafreniere, Philip. “IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING.” 2015. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/25757.

MLA Handbook (7th Edition):

Lafreniere, Philip. “IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING.” 2015. Web. 25 Jun 2019.

Vancouver:

Lafreniere P. IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING. [Internet] [Masters thesis]. University of New Mexico; 2015. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/25757.

Council of Science Editors:

Lafreniere P. IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING. [Masters Thesis]. University of New Mexico; 2015. Available from: http://hdl.handle.net/1928/25757


University of New Mexico

15. Long, Joel. A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor.

Degree: Nuclear Engineering, 2016, University of New Mexico

 This thesis describes a heavy-ion recoil neutron spectrometer as an alternative to existing magnetic proton recoil neutron spectrometers for inertial confinement fusion experiments. Whereas existing… (more)

Subjects/Keywords: Neutron Spectrometer; Pulsed Power; Fusion; Energy; Semiconductor Sensor; Heavy Ions; Recoil Spectrometer

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APA (6th Edition):

Long, J. (2016). A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/31675

Chicago Manual of Style (16th Edition):

Long, Joel. “A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor.” 2016. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/31675.

MLA Handbook (7th Edition):

Long, Joel. “A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor.” 2016. Web. 25 Jun 2019.

Vancouver:

Long J. A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor. [Internet] [Masters thesis]. University of New Mexico; 2016. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/31675.

Council of Science Editors:

Long J. A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor. [Masters Thesis]. University of New Mexico; 2016. Available from: http://hdl.handle.net/1928/31675


University of New Mexico

16. Smith, Paul. Analysis of moment-preserving methods for charged particle transport.

Degree: Nuclear Engineering, 2009, University of New Mexico

 The simulation of electrons, protons, and other charged particles can be an expensive computation. On the one hand, the small mean free path of a… (more)

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APA (6th Edition):

Smith, P. (2009). Analysis of moment-preserving methods for charged particle transport. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/9802

Chicago Manual of Style (16th Edition):

Smith, Paul. “Analysis of moment-preserving methods for charged particle transport.” 2009. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/9802.

MLA Handbook (7th Edition):

Smith, Paul. “Analysis of moment-preserving methods for charged particle transport.” 2009. Web. 25 Jun 2019.

Vancouver:

Smith P. Analysis of moment-preserving methods for charged particle transport. [Internet] [Masters thesis]. University of New Mexico; 2009. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/9802.

Council of Science Editors:

Smith P. Analysis of moment-preserving methods for charged particle transport. [Masters Thesis]. University of New Mexico; 2009. Available from: http://hdl.handle.net/1928/9802


University of New Mexico

17. Gregson, Michael. Time dependent non-extinction probability for fast burst reactors.

Degree: Nuclear Engineering, 2009, University of New Mexico

  Sandia National Laboratories has successfully operated fast burst reactors over the past four decades. Fast burst reactors refer to a type of reactor that… (more)

Subjects/Keywords: Pulsed reactors – Mathematical models.; Nuclear reactors – Reactivity – Mathematical models.; Nuclear reactor kinetics – Mathematical models.; Nuclear Engineering

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APA (6th Edition):

Gregson, M. (2009). Time dependent non-extinction probability for fast burst reactors. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/9319

Chicago Manual of Style (16th Edition):

Gregson, Michael. “Time dependent non-extinction probability for fast burst reactors.” 2009. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/9319.

MLA Handbook (7th Edition):

Gregson, Michael. “Time dependent non-extinction probability for fast burst reactors.” 2009. Web. 25 Jun 2019.

Vancouver:

Gregson M. Time dependent non-extinction probability for fast burst reactors. [Internet] [Doctoral dissertation]. University of New Mexico; 2009. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/9319.

Council of Science Editors:

Gregson M. Time dependent non-extinction probability for fast burst reactors. [Doctoral Dissertation]. University of New Mexico; 2009. Available from: http://hdl.handle.net/1928/9319


University of New Mexico

18. Zohuri, Bahman. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.

Degree: Nuclear Engineering, 2014, University of New Mexico

 The purpose of this research was to model and analyze a nuclear heated multi-turbine power conversion system operating with atmospheric air as the working fluid.… (more)

Subjects/Keywords: Brayton-Rankine combined cycle; Recuperated Brayton; generation IV nuclear power plants

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APA (6th Edition):

Zohuri, B. (2014). INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24364

Chicago Manual of Style (16th Edition):

Zohuri, Bahman. “INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.” 2014. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/24364.

MLA Handbook (7th Edition):

Zohuri, Bahman. “INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.” 2014. Web. 25 Jun 2019.

Vancouver:

Zohuri B. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. [Internet] [Doctoral dissertation]. University of New Mexico; 2014. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/24364.

Council of Science Editors:

Zohuri B. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. [Doctoral Dissertation]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24364


University of New Mexico

19. Dixon, David. A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4.

Degree: Nuclear Engineering, 2015, University of New Mexico

 The subject of this dissertation is a moment-preserving Monte Carlo electron transport method that is more efficient than analog or detailed Monte Carlo simulations, yet… (more)

Subjects/Keywords: Monte Carlo; Electron Transport; Moment-preservation

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APA (6th Edition):

Dixon, D. (2015). A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/27772

Chicago Manual of Style (16th Edition):

Dixon, David. “A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4.” 2015. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/27772.

MLA Handbook (7th Edition):

Dixon, David. “A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4.” 2015. Web. 25 Jun 2019.

Vancouver:

Dixon D. A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4. [Internet] [Doctoral dissertation]. University of New Mexico; 2015. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/27772.

Council of Science Editors:

Dixon D. A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4. [Doctoral Dissertation]. University of New Mexico; 2015. Available from: http://hdl.handle.net/1928/27772


University of New Mexico

20. Fichtl, Christopher. An arbitrary curvilinear coordinate particle in cell method.

Degree: Nuclear Engineering, 2010, University of New Mexico

 A new approach to the kinetic simulation of plasmas in complex geometries, based on the Particle-in-Cell (PIC) simulation method, is explored. In this method, called… (more)

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APA (6th Edition):

Fichtl, C. (2010). An arbitrary curvilinear coordinate particle in cell method. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/11152

Chicago Manual of Style (16th Edition):

Fichtl, Christopher. “An arbitrary curvilinear coordinate particle in cell method.” 2010. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/11152.

MLA Handbook (7th Edition):

Fichtl, Christopher. “An arbitrary curvilinear coordinate particle in cell method.” 2010. Web. 25 Jun 2019.

Vancouver:

Fichtl C. An arbitrary curvilinear coordinate particle in cell method. [Internet] [Doctoral dissertation]. University of New Mexico; 2010. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/11152.

Council of Science Editors:

Fichtl C. An arbitrary curvilinear coordinate particle in cell method. [Doctoral Dissertation]. University of New Mexico; 2010. Available from: http://hdl.handle.net/1928/11152


University of New Mexico

21. Martin, William. Dual neutral particle induced transmutation.

Degree: Nuclear Engineering, 2012, University of New Mexico

 Although nuclear transmutation methods have been around for decades, they all focus solely on neutron induced reactions. Recent novel concepts have sought to use neutrons… (more)

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APA (6th Edition):

Martin, W. (2012). Dual neutral particle induced transmutation. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/20845

Chicago Manual of Style (16th Edition):

Martin, William. “Dual neutral particle induced transmutation.” 2012. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/20845.

MLA Handbook (7th Edition):

Martin, William. “Dual neutral particle induced transmutation.” 2012. Web. 25 Jun 2019.

Vancouver:

Martin W. Dual neutral particle induced transmutation. [Internet] [Doctoral dissertation]. University of New Mexico; 2012. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/20845.

Council of Science Editors:

Martin W. Dual neutral particle induced transmutation. [Doctoral Dissertation]. University of New Mexico; 2012. Available from: http://hdl.handle.net/1928/20845


University of New Mexico

22. Martin, William. Nonlinear acceleration methods for even-parity neutron transport.

Degree: Nuclear Engineering, 2010, University of New Mexico

 Convergence acceleration methods for even-parity transport are being developed that have the potential to speed up transport calculations and provide a natural avenue for an… (more)

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APA (6th Edition):

Martin, W. (2010). Nonlinear acceleration methods for even-parity neutron transport. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/10832

Chicago Manual of Style (16th Edition):

Martin, William. “Nonlinear acceleration methods for even-parity neutron transport.” 2010. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/10832.

MLA Handbook (7th Edition):

Martin, William. “Nonlinear acceleration methods for even-parity neutron transport.” 2010. Web. 25 Jun 2019.

Vancouver:

Martin W. Nonlinear acceleration methods for even-parity neutron transport. [Internet] [Masters thesis]. University of New Mexico; 2010. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/10832.

Council of Science Editors:

Martin W. Nonlinear acceleration methods for even-parity neutron transport. [Masters Thesis]. University of New Mexico; 2010. Available from: http://hdl.handle.net/1928/10832


University of New Mexico

23. Danly, Christopher. Radiation Damage in Permanent Magnet Lenses.

Degree: Nuclear Engineering, 2014, University of New Mexico

 Proton radiography techniques in use at Los Alamos National Lab and elsewhere depend upon permanent magnet quadrupoles in their magnetic optics. Radiation exposure during radiography… (more)

Subjects/Keywords: magnet; PMQ; radiography

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APA (6th Edition):

Danly, C. (2014). Radiation Damage in Permanent Magnet Lenses. (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24477

Chicago Manual of Style (16th Edition):

Danly, Christopher. “Radiation Damage in Permanent Magnet Lenses.” 2014. Masters Thesis, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/24477.

MLA Handbook (7th Edition):

Danly, Christopher. “Radiation Damage in Permanent Magnet Lenses.” 2014. Web. 25 Jun 2019.

Vancouver:

Danly C. Radiation Damage in Permanent Magnet Lenses. [Internet] [Masters thesis]. University of New Mexico; 2014. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/24477.

Council of Science Editors:

Danly C. Radiation Damage in Permanent Magnet Lenses. [Masters Thesis]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24477


University of New Mexico

24. Fichtl, Erin D. Stochastic methods for uncertainty quantification in radiation transport.

Degree: Nuclear Engineering, 2009, University of New Mexico

  The use of stochastic spectral expansions, specifically generalized polynomial chaos (gPC) and Karhunen-Loeve (KL) expansions, is investigated for uncertainty quantification in radiation transport. The… (more)

Subjects/Keywords: Transport theory – Statistical methods.; Neutron transport theory – Statistical methods.; Collocation methods.; Finite element method.; Uncertainty – Mathematical models.; Nuclear Engineering

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

APA (6th Edition):

Fichtl, E. D. (2009). Stochastic methods for uncertainty quantification in radiation transport. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/9337

Chicago Manual of Style (16th Edition):

Fichtl, Erin D. “Stochastic methods for uncertainty quantification in radiation transport.” 2009. Doctoral Dissertation, University of New Mexico. Accessed June 25, 2019. http://hdl.handle.net/1928/9337.

MLA Handbook (7th Edition):

Fichtl, Erin D. “Stochastic methods for uncertainty quantification in radiation transport.” 2009. Web. 25 Jun 2019.

Vancouver:

Fichtl ED. Stochastic methods for uncertainty quantification in radiation transport. [Internet] [Doctoral dissertation]. University of New Mexico; 2009. [cited 2019 Jun 25]. Available from: http://hdl.handle.net/1928/9337.

Council of Science Editors:

Fichtl ED. Stochastic methods for uncertainty quantification in radiation transport. [Doctoral Dissertation]. University of New Mexico; 2009. Available from: http://hdl.handle.net/1928/9337

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