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You searched for +publisher:"Oregon State University" +contributor:("Palmer, Todd S."). Showing records 1 – 30 of 37 total matches.

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Oregon State University

1. MacQuigg, Michael R. Pair production treatments for deterministic pulse-height distribution simulations.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 This thesis presents methods for treating annihilation photon pairs in deterministic pulse height distribution (PHD) simulations. The methods are applied in PHD simulations for monoenergtic… (more)

Subjects/Keywords: pulse height distribution; Pulse height analyzers

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APA (6th Edition):

MacQuigg, M. R. (2011). Pair production treatments for deterministic pulse-height distribution simulations. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/23889

Chicago Manual of Style (16th Edition):

MacQuigg, Michael R. “Pair production treatments for deterministic pulse-height distribution simulations.” 2011. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/23889.

MLA Handbook (7th Edition):

MacQuigg, Michael R. “Pair production treatments for deterministic pulse-height distribution simulations.” 2011. Web. 15 Feb 2019.

Vancouver:

MacQuigg MR. Pair production treatments for deterministic pulse-height distribution simulations. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/23889.

Council of Science Editors:

MacQuigg MR. Pair production treatments for deterministic pulse-height distribution simulations. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/23889


Oregon State University

2. Soldatov, Alexey I. Design and analysis of a nuclear reactor core for innovative small light water reactors.

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

 In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR)… (more)

Subjects/Keywords: Nuclear Reactor; Light water reactors  – Design and construction

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APA (6th Edition):

Soldatov, A. I. (2009). Design and analysis of a nuclear reactor core for innovative small light water reactors. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/11315

Chicago Manual of Style (16th Edition):

Soldatov, Alexey I. “Design and analysis of a nuclear reactor core for innovative small light water reactors.” 2009. Doctoral Dissertation, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/11315.

MLA Handbook (7th Edition):

Soldatov, Alexey I. “Design and analysis of a nuclear reactor core for innovative small light water reactors.” 2009. Web. 15 Feb 2019.

Vancouver:

Soldatov AI. Design and analysis of a nuclear reactor core for innovative small light water reactors. [Internet] [Doctoral dissertation]. Oregon State University; 2009. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/11315.

Council of Science Editors:

Soldatov AI. Design and analysis of a nuclear reactor core for innovative small light water reactors. [Doctoral Dissertation]. Oregon State University; 2009. Available from: http://hdl.handle.net/1957/11315


Oregon State University

3. Hummel, Andrew J. Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 Reactor modeling is largely limited by the computational time required to perform accurate full core calculations. There are many different methods and techniques employed in… (more)

Subjects/Keywords: PARCS

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APA (6th Edition):

Hummel, A. J. (2011). Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/20859

Chicago Manual of Style (16th Edition):

Hummel, Andrew J. “Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry.” 2011. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/20859.

MLA Handbook (7th Edition):

Hummel, Andrew J. “Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry.” 2011. Web. 15 Feb 2019.

Vancouver:

Hummel AJ. Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/20859.

Council of Science Editors:

Hummel AJ. Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/20859


Oregon State University

4. Elliott, Anthony James. Radioxenon generation using highly enriched uranium.

Degree: MS, Nuclear Engineering, 2008, Oregon State University

 This work focuses on the generation and collection of four specific radioxenon isotopes; xenon-131m, xenon-133m, xenon-133 and xenon-135. These nuclides are created by fissioning a… (more)

Subjects/Keywords: nuclear; Xenon  – Isotopes

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APA (6th Edition):

Elliott, A. J. (2008). Radioxenon generation using highly enriched uranium. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/9244

Chicago Manual of Style (16th Edition):

Elliott, Anthony James. “Radioxenon generation using highly enriched uranium.” 2008. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/9244.

MLA Handbook (7th Edition):

Elliott, Anthony James. “Radioxenon generation using highly enriched uranium.” 2008. Web. 15 Feb 2019.

Vancouver:

Elliott AJ. Radioxenon generation using highly enriched uranium. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/9244.

Council of Science Editors:

Elliott AJ. Radioxenon generation using highly enriched uranium. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/9244


Oregon State University

5. Francy, Christopher J. Detection of actinides via nuclear isomer de-excitation.

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

 The detection of illicit weapons-grade nuclear material is a significant technical challenge receiving a great deal of attention in the nuclear community. A proposed solution… (more)

Subjects/Keywords: Isomers; Actinide elements

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APA (6th Edition):

Francy, C. J. (2009). Detection of actinides via nuclear isomer de-excitation. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/12114

Chicago Manual of Style (16th Edition):

Francy, Christopher J. “Detection of actinides via nuclear isomer de-excitation.” 2009. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/12114.

MLA Handbook (7th Edition):

Francy, Christopher J. “Detection of actinides via nuclear isomer de-excitation.” 2009. Web. 15 Feb 2019.

Vancouver:

Francy CJ. Detection of actinides via nuclear isomer de-excitation. [Internet] [Masters thesis]. Oregon State University; 2009. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/12114.

Council of Science Editors:

Francy CJ. Detection of actinides via nuclear isomer de-excitation. [Masters Thesis]. Oregon State University; 2009. Available from: http://hdl.handle.net/1957/12114


Oregon State University

6. Somasundaram, Elanchezhian. Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems.

Degree: PhD, Nuclear Engineering, 2015, Oregon State University

 The implementation of advanced hybrid (Monte Carlo/Deterministic) transport methods for realistic test problems has been a challenge due to the overhead efforts associated with interfacing… (more)

Subjects/Keywords: Variance reduction techniques; Radiative transfer  – Mathematical models

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APA (6th Edition):

Somasundaram, E. (2015). Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/57268

Chicago Manual of Style (16th Edition):

Somasundaram, Elanchezhian. “Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems.” 2015. Doctoral Dissertation, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/57268.

MLA Handbook (7th Edition):

Somasundaram, Elanchezhian. “Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems.” 2015. Web. 15 Feb 2019.

Vancouver:

Somasundaram E. Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems. [Internet] [Doctoral dissertation]. Oregon State University; 2015. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/57268.

Council of Science Editors:

Somasundaram E. Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems. [Doctoral Dissertation]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/57268


Oregon State University

7. Alberti, Anthony L. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.

Degree: MS, Nuclear Engineering, 2015, Oregon State University

 With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption… (more)

Subjects/Keywords: TREAT; Nuclear fuels  – Testing

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APA (6th Edition):

Alberti, A. L. (2015). Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/58315

Chicago Manual of Style (16th Edition):

Alberti, Anthony L. “Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.” 2015. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/58315.

MLA Handbook (7th Edition):

Alberti, Anthony L. “Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.” 2015. Web. 15 Feb 2019.

Vancouver:

Alberti AL. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/58315.

Council of Science Editors:

Alberti AL. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. [Masters Thesis]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/58315


Oregon State University

8. Woods, Douglas N. High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit.

Degree: MS, Nuclear Engineering, 2016, Oregon State University

 The high-order finite element S[subscript N] transport equations are solved on several test problems to investigate the behavior of the discretization method on meshes with… (more)

Subjects/Keywords: finite elements; Radiative transfer  – Mathematical models

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APA (6th Edition):

Woods, D. N. (2016). High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/58954

Chicago Manual of Style (16th Edition):

Woods, Douglas N. “High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit.” 2016. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/58954.

MLA Handbook (7th Edition):

Woods, Douglas N. “High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit.” 2016. Web. 15 Feb 2019.

Vancouver:

Woods DN. High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/58954.

Council of Science Editors:

Woods DN. High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/58954


Oregon State University

9. Shaughnessy, Andra L. Predicting antineutrino source terms from a high temperature gas reactor.

Degree: MS, Nuclear Engineering, 2012, Oregon State University

 Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors… (more)

Subjects/Keywords: antineutrino; Antineutrinos

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APA (6th Edition):

Shaughnessy, A. L. (2012). Predicting antineutrino source terms from a high temperature gas reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/29045

Chicago Manual of Style (16th Edition):

Shaughnessy, Andra L. “Predicting antineutrino source terms from a high temperature gas reactor.” 2012. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/29045.

MLA Handbook (7th Edition):

Shaughnessy, Andra L. “Predicting antineutrino source terms from a high temperature gas reactor.” 2012. Web. 15 Feb 2019.

Vancouver:

Shaughnessy AL. Predicting antineutrino source terms from a high temperature gas reactor. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/29045.

Council of Science Editors:

Shaughnessy AL. Predicting antineutrino source terms from a high temperature gas reactor. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/29045


Oregon State University

10. Peguero, Lara M. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.

Degree: MS, Nuclear Engineering, 2016, Oregon State University

 Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of… (more)

Subjects/Keywords: Reactor physics; Light water reactors  – Uzbekistan

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APA (6th Edition):

Peguero, L. M. (2016). Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/59812

Chicago Manual of Style (16th Edition):

Peguero, Lara M. “Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.” 2016. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/59812.

MLA Handbook (7th Edition):

Peguero, Lara M. “Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.” 2016. Web. 15 Feb 2019.

Vancouver:

Peguero LM. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/59812.

Council of Science Editors:

Peguero LM. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/59812


Oregon State University

11. Talbot, Paul W. Extending the discrete maximum principle for the IMC equations.

Degree: MS, Nuclear Engineering, 2012, Oregon State University

 The implicit Monte Carlo (IMC) method [16] for radiative transfer, developed in 1971, provides numerical solutions to the tightly-coupled, highly-nonlinear radiative heat transfer equations in… (more)

Subjects/Keywords: Monte Carlo method

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APA (6th Edition):

Talbot, P. W. (2012). Extending the discrete maximum principle for the IMC equations. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/36503

Chicago Manual of Style (16th Edition):

Talbot, Paul W. “Extending the discrete maximum principle for the IMC equations.” 2012. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/36503.

MLA Handbook (7th Edition):

Talbot, Paul W. “Extending the discrete maximum principle for the IMC equations.” 2012. Web. 15 Feb 2019.

Vancouver:

Talbot PW. Extending the discrete maximum principle for the IMC equations. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/36503.

Council of Science Editors:

Talbot PW. Extending the discrete maximum principle for the IMC equations. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/36503


Oregon State University

12. Benz, Jacob M. Calculation of Pulse height distributions from deterministic transport simulations.

Degree: MS, Nuclear Engineering, 2008, Oregon State University

 In source-detector radiation transport simulations, pulse height distributions are a useful metric in assessing the effectiveness of nuclear instrumentation. In the area of spectroscopy, pulse… (more)

Subjects/Keywords: Pulse Height Distribution; Pulse height analyzers

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APA (6th Edition):

Benz, J. M. (2008). Calculation of Pulse height distributions from deterministic transport simulations. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/8897

Chicago Manual of Style (16th Edition):

Benz, Jacob M. “Calculation of Pulse height distributions from deterministic transport simulations.” 2008. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/8897.

MLA Handbook (7th Edition):

Benz, Jacob M. “Calculation of Pulse height distributions from deterministic transport simulations.” 2008. Web. 15 Feb 2019.

Vancouver:

Benz JM. Calculation of Pulse height distributions from deterministic transport simulations. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/8897.

Council of Science Editors:

Benz JM. Calculation of Pulse height distributions from deterministic transport simulations. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/8897


Oregon State University

13. Nakagawa, Ayako. Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts.

Degree: MS, Chemical Engineering, 2008, Oregon State University

 Influences of operating conditions on the production of carbon nanotubes (CNTs) were studied using Fe and Fe-Ni bimetallic catalysts supported on silicon monoxide (SiO). The… (more)

Subjects/Keywords: carbon nanotubes; Nanotubes  – Synthesis

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APA (6th Edition):

Nakagawa, A. (2008). Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/9151

Chicago Manual of Style (16th Edition):

Nakagawa, Ayako. “Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts.” 2008. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/9151.

MLA Handbook (7th Edition):

Nakagawa, Ayako. “Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts.” 2008. Web. 15 Feb 2019.

Vancouver:

Nakagawa A. Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/9151.

Council of Science Editors:

Nakagawa A. Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/9151

14. Ryan, Michael C. (Michael Colin). Characterization of the onset of charged particle equilibrium for photon dose to skin.

Degree: MS, Medical Physics, 2010, Oregon State University

 In the U.S., the Nuclear Regulatory Commission (NRC) is responsible for setting annual dose limits. For cases of hot particle contamination these limits are set… (more)

Subjects/Keywords: charged particle equilibrium; Photons  – Measurement

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APA (6th Edition):

Ryan, M. C. (. C. (2010). Characterization of the onset of charged particle equilibrium for photon dose to skin. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/16398

Chicago Manual of Style (16th Edition):

Ryan, Michael C (Michael Colin). “Characterization of the onset of charged particle equilibrium for photon dose to skin.” 2010. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/16398.

MLA Handbook (7th Edition):

Ryan, Michael C (Michael Colin). “Characterization of the onset of charged particle equilibrium for photon dose to skin.” 2010. Web. 15 Feb 2019.

Vancouver:

Ryan MC(C. Characterization of the onset of charged particle equilibrium for photon dose to skin. [Internet] [Masters thesis]. Oregon State University; 2010. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/16398.

Council of Science Editors:

Ryan MC(C. Characterization of the onset of charged particle equilibrium for photon dose to skin. [Masters Thesis]. Oregon State University; 2010. Available from: http://hdl.handle.net/1957/16398

15. Bassett, Brody R. An assessment of a mesh-based method for slab-geometry transport in stochastic materials.

Degree: MS, Nuclear Engineering, 2014, Oregon State University

 There exists a variety of methods to solve the radiation transport equation in stochastic materials, including the Levermore-Pomraning method and the atomic mix method, each… (more)

Subjects/Keywords: Neutron transport theory  – Mathematical models

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APA (6th Edition):

Bassett, B. R. (2014). An assessment of a mesh-based method for slab-geometry transport in stochastic materials. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/52587

Chicago Manual of Style (16th Edition):

Bassett, Brody R. “An assessment of a mesh-based method for slab-geometry transport in stochastic materials.” 2014. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/52587.

MLA Handbook (7th Edition):

Bassett, Brody R. “An assessment of a mesh-based method for slab-geometry transport in stochastic materials.” 2014. Web. 15 Feb 2019.

Vancouver:

Bassett BR. An assessment of a mesh-based method for slab-geometry transport in stochastic materials. [Internet] [Masters thesis]. Oregon State University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/52587.

Council of Science Editors:

Bassett BR. An assessment of a mesh-based method for slab-geometry transport in stochastic materials. [Masters Thesis]. Oregon State University; 2014. Available from: http://hdl.handle.net/1957/52587

16. Matthews, Christopher. Fission Gas Bubble Behavior in Uranium Carbide.

Degree: PhD, Nuclear Engineering, 2015, Oregon State University

 The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor… (more)

Subjects/Keywords: Fission Gas Release; Uranium compounds

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APA (6th Edition):

Matthews, C. (2015). Fission Gas Bubble Behavior in Uranium Carbide. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/56137

Chicago Manual of Style (16th Edition):

Matthews, Christopher. “Fission Gas Bubble Behavior in Uranium Carbide.” 2015. Doctoral Dissertation, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/56137.

MLA Handbook (7th Edition):

Matthews, Christopher. “Fission Gas Bubble Behavior in Uranium Carbide.” 2015. Web. 15 Feb 2019.

Vancouver:

Matthews C. Fission Gas Bubble Behavior in Uranium Carbide. [Internet] [Doctoral dissertation]. Oregon State University; 2015. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/56137.

Council of Science Editors:

Matthews C. Fission Gas Bubble Behavior in Uranium Carbide. [Doctoral Dissertation]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56137

17. Bevill, Aaron M. Performance of hybrid methods for representative nonproliferation problems.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 Adjoint-derived weight windowing is a hybrid deterministic/Monte Carlo method to simulate radiation transport. In adjoint-derived weight windowing, a deterministic adjoint solution is used to create… (more)

Subjects/Keywords: radiation transport; Radiative transfer

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APA (6th Edition):

Bevill, A. M. (2011). Performance of hybrid methods for representative nonproliferation problems. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/21643

Chicago Manual of Style (16th Edition):

Bevill, Aaron M. “Performance of hybrid methods for representative nonproliferation problems.” 2011. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/21643.

MLA Handbook (7th Edition):

Bevill, Aaron M. “Performance of hybrid methods for representative nonproliferation problems.” 2011. Web. 15 Feb 2019.

Vancouver:

Bevill AM. Performance of hybrid methods for representative nonproliferation problems. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/21643.

Council of Science Editors:

Bevill AM. Performance of hybrid methods for representative nonproliferation problems. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/21643

18. Myers, Nicholas T. Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 The objective of this thesis was to investigate the use of the Jacobian Free Newton Krylov Method (JFNK) with physics based preconditioning for solving coupled… (more)

Subjects/Keywords: JFNK

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APA (6th Edition):

Myers, N. T. (2011). Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/21698

Chicago Manual of Style (16th Edition):

Myers, Nicholas T. “Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling.” 2011. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/21698.

MLA Handbook (7th Edition):

Myers, Nicholas T. “Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling.” 2011. Web. 15 Feb 2019.

Vancouver:

Myers NT. Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/21698.

Council of Science Editors:

Myers NT. Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/21698

19. Long, Alex R. The iterative thermal emission Monte Carlo method for thermal radiative transfer.

Degree: MS, Nuclear Engineering, 2012, Oregon State University

 For over 30 years, the Implicit Monte Carlo (IMC) method has been used to solve challenging problems in thermal radiative transfer. These problems are typically… (more)

Subjects/Keywords: Particle Transport; Radiative transfer  – Mathematical models

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APA (6th Edition):

Long, A. R. (2012). The iterative thermal emission Monte Carlo method for thermal radiative transfer. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/33215

Chicago Manual of Style (16th Edition):

Long, Alex R. “The iterative thermal emission Monte Carlo method for thermal radiative transfer.” 2012. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/33215.

MLA Handbook (7th Edition):

Long, Alex R. “The iterative thermal emission Monte Carlo method for thermal radiative transfer.” 2012. Web. 15 Feb 2019.

Vancouver:

Long AR. The iterative thermal emission Monte Carlo method for thermal radiative transfer. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/33215.

Council of Science Editors:

Long AR. The iterative thermal emission Monte Carlo method for thermal radiative transfer. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/33215

20. Somasundaram, Elanchezhian. Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 Detection of reactor antineutrinos for non-proliferation applications has been researched extensively across the globe and is considered as a potential technology to remotely monitor reactor… (more)

Subjects/Keywords: Antineutrino Source Terms; Antineutrinos

…x29; is a 45 MWe modular reactor design developed at Oregon State University 26 in… 

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APA (6th Edition):

Somasundaram, E. (2011). Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/25131

Chicago Manual of Style (16th Edition):

Somasundaram, Elanchezhian. “Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios.” 2011. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/25131.

MLA Handbook (7th Edition):

Somasundaram, Elanchezhian. “Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios.” 2011. Web. 15 Feb 2019.

Vancouver:

Somasundaram E. Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/25131.

Council of Science Editors:

Somasundaram E. Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/25131

21. Lenhof, Renae. Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant.

Degree: MS, Nuclear Engineering, 2014, Oregon State University

 A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal… (more)

Subjects/Keywords: PRA; Gas cooled reactors  – Safety measures

…research conducted at Oregon State University (OSU) under funding by the U.S… 

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APA (6th Edition):

Lenhof, R. (2014). Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/52593

Chicago Manual of Style (16th Edition):

Lenhof, Renae. “Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant.” 2014. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/52593.

MLA Handbook (7th Edition):

Lenhof, Renae. “Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant.” 2014. Web. 15 Feb 2019.

Vancouver:

Lenhof R. Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant. [Internet] [Masters thesis]. Oregon State University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/52593.

Council of Science Editors:

Lenhof R. Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant. [Masters Thesis]. Oregon State University; 2014. Available from: http://hdl.handle.net/1957/52593

22. Matthews, Christopher. Analysis of the antineutrino rate during CANDU reactor startup.

Degree: MS, Nuclear Engineering, 2012, Oregon State University

 Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to… (more)

Subjects/Keywords: CANDU; Antineutrinos

…power monitor in the MASLWR, a small 150 MWth modular reactor design from Oregon State… …University (OSU). The SONGS detector was predicted to measure the hourly average power to… 

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APA (6th Edition):

Matthews, C. (2012). Analysis of the antineutrino rate during CANDU reactor startup. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/27973

Chicago Manual of Style (16th Edition):

Matthews, Christopher. “Analysis of the antineutrino rate during CANDU reactor startup.” 2012. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/27973.

MLA Handbook (7th Edition):

Matthews, Christopher. “Analysis of the antineutrino rate during CANDU reactor startup.” 2012. Web. 15 Feb 2019.

Vancouver:

Matthews C. Analysis of the antineutrino rate during CANDU reactor startup. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/27973.

Council of Science Editors:

Matthews C. Analysis of the antineutrino rate during CANDU reactor startup. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/27973

23. Rising, Michael E. Analysis of the method of tubes characteristic schemes in the thick diffusive limit.

Degree: MS, Nuclear Engineering, 2008, Oregon State University

 Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport problems. These methods are most often used for neutron… (more)

Subjects/Keywords: Thermal Radiative Transfer; Transport theory  – Mathematical models

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APA (6th Edition):

Rising, M. E. (2008). Analysis of the method of tubes characteristic schemes in the thick diffusive limit. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/8916

Chicago Manual of Style (16th Edition):

Rising, Michael E. “Analysis of the method of tubes characteristic schemes in the thick diffusive limit.” 2008. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/8916.

MLA Handbook (7th Edition):

Rising, Michael E. “Analysis of the method of tubes characteristic schemes in the thick diffusive limit.” 2008. Web. 15 Feb 2019.

Vancouver:

Rising ME. Analysis of the method of tubes characteristic schemes in the thick diffusive limit. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/8916.

Council of Science Editors:

Rising ME. Analysis of the method of tubes characteristic schemes in the thick diffusive limit. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/8916


Oregon State University

24. Laubsch, Bertrand. Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT.

Degree: MS, Physics, 2000, Oregon State University

 Spatially discretized diffusion approximation equations are derived directly from spatially discretized radiation transport equations in 1-D slab geometry. Derivations for isotropic diffusion theory (IDT) and… (more)

Subjects/Keywords: Transport theory

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APA (6th Edition):

Laubsch, B. (2000). Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/33010

Chicago Manual of Style (16th Edition):

Laubsch, Bertrand. “Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT.” 2000. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/33010.

MLA Handbook (7th Edition):

Laubsch, Bertrand. “Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT.” 2000. Web. 15 Feb 2019.

Vancouver:

Laubsch B. Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT. [Internet] [Masters thesis]. Oregon State University; 2000. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/33010.

Council of Science Editors:

Laubsch B. Flux-limited diffusion theory for spatially discretized equations : a discretized derivation of Levermore-Pomraning FLDT. [Masters Thesis]. Oregon State University; 2000. Available from: http://hdl.handle.net/1957/33010


Oregon State University

25. Brice, Derek J. MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant.

Degree: MS, Nuclear Engineering, 1998, Oregon State University

Subjects/Keywords: Spent reactor fuels  – Storage  – Oregon

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APA (6th Edition):

Brice, D. J. (1998). MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/33821

Chicago Manual of Style (16th Edition):

Brice, Derek J. “MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant.” 1998. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/33821.

MLA Handbook (7th Edition):

Brice, Derek J. “MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant.” 1998. Web. 15 Feb 2019.

Vancouver:

Brice DJ. MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant. [Internet] [Masters thesis]. Oregon State University; 1998. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/33821.

Council of Science Editors:

Brice DJ. MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant. [Masters Thesis]. Oregon State University; 1998. Available from: http://hdl.handle.net/1957/33821


Oregon State University

26. Strohecker, Mark F. Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility.

Degree: MS, Nuclear Engineering, 1998, Oregon State University

 The OSU/APEX thermal hydraulic test facility models the passive safety systems of the Westinghouse AP600 advanced light water reactor design. Numerous experiments have been performed… (more)

Subjects/Keywords: Nuclear power plants  – Thermodynamics

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APA (6th Edition):

Strohecker, M. F. (1998). Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/34520

Chicago Manual of Style (16th Edition):

Strohecker, Mark F. “Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility.” 1998. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/34520.

MLA Handbook (7th Edition):

Strohecker, Mark F. “Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility.” 1998. Web. 15 Feb 2019.

Vancouver:

Strohecker MF. Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility. [Internet] [Masters thesis]. Oregon State University; 1998. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/34520.

Council of Science Editors:

Strohecker MF. Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility. [Masters Thesis]. Oregon State University; 1998. Available from: http://hdl.handle.net/1957/34520


Oregon State University

27. Stringham, Michael J. Predicting dose and cell survival distributions for brachytherapy sources.

Degree: MS, Nuclear Engineering, 2003, Oregon State University

Subjects/Keywords: Radioisotope brachytherapy

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APA (6th Edition):

Stringham, M. J. (2003). Predicting dose and cell survival distributions for brachytherapy sources. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/22486

Chicago Manual of Style (16th Edition):

Stringham, Michael J. “Predicting dose and cell survival distributions for brachytherapy sources.” 2003. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/22486.

MLA Handbook (7th Edition):

Stringham, Michael J. “Predicting dose and cell survival distributions for brachytherapy sources.” 2003. Web. 15 Feb 2019.

Vancouver:

Stringham MJ. Predicting dose and cell survival distributions for brachytherapy sources. [Internet] [Masters thesis]. Oregon State University; 2003. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/22486.

Council of Science Editors:

Stringham MJ. Predicting dose and cell survival distributions for brachytherapy sources. [Masters Thesis]. Oregon State University; 2003. Available from: http://hdl.handle.net/1957/22486


Oregon State University

28. Misner, Alex C. Modeling radiation and hydrogen production in a radioisotope micro-power source.

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

 Radioisotope based power systems have been used for several decades. This research covers a new concept in the field, a radioisotope micro-power source (RIMS). A… (more)

Subjects/Keywords: Isotopic power generators

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APA (6th Edition):

Misner, A. C. (2005). Modeling radiation and hydrogen production in a radioisotope micro-power source. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/22618

Chicago Manual of Style (16th Edition):

Misner, Alex C. “Modeling radiation and hydrogen production in a radioisotope micro-power source.” 2005. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/22618.

MLA Handbook (7th Edition):

Misner, Alex C. “Modeling radiation and hydrogen production in a radioisotope micro-power source.” 2005. Web. 15 Feb 2019.

Vancouver:

Misner AC. Modeling radiation and hydrogen production in a radioisotope micro-power source. [Internet] [Masters thesis]. Oregon State University; 2005. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/22618.

Council of Science Editors:

Misner AC. Modeling radiation and hydrogen production in a radioisotope micro-power source. [Masters Thesis]. Oregon State University; 2005. Available from: http://hdl.handle.net/1957/22618


Oregon State University

29. 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 February 15, 2019. http://hdl.handle.net/1957/29748.

MLA Handbook (7th Edition):

Davis, Ian M (Ian Mack). “Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups.” 2005. Web. 15 Feb 2019.

Vancouver:

Davis IM(M. Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups. [Internet] [Masters thesis]. Oregon State University; 2005. [cited 2019 Feb 15]. 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


Oregon State University

30. Nes, Razvan. An advanced nodal discretization for the quasi-diffusion low-order equations.

Degree: MS, Nuclear Engineering, 2002, Oregon State University

 The subject of this thesis is the development of a nodal discretization of the low-order quasi-diffusion (QDLO) equations for global reactor core calculations. The advantage… (more)

Subjects/Keywords: Neutron flux  – Mathematical models

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APA (6th Edition):

Nes, R. (2002). An advanced nodal discretization for the quasi-diffusion low-order equations. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/30335

Chicago Manual of Style (16th Edition):

Nes, Razvan. “An advanced nodal discretization for the quasi-diffusion low-order equations.” 2002. Masters Thesis, Oregon State University. Accessed February 15, 2019. http://hdl.handle.net/1957/30335.

MLA Handbook (7th Edition):

Nes, Razvan. “An advanced nodal discretization for the quasi-diffusion low-order equations.” 2002. Web. 15 Feb 2019.

Vancouver:

Nes R. An advanced nodal discretization for the quasi-diffusion low-order equations. [Internet] [Masters thesis]. Oregon State University; 2002. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/1957/30335.

Council of Science Editors:

Nes R. An advanced nodal discretization for the quasi-diffusion low-order equations. [Masters Thesis]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/30335

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