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You searched for subject:(nuclear reactor physics). Showing records 1 – 30 of 48 total matches.

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The Ohio State University

1. Kennedy, Ryanne Ariel. Quantifying Uncertainty in Reactor Flux/Power Distributions.

Degree: PhD, Nuclear Engineering, 2011, The Ohio State University

 The design and development of a conceptual system for power measurements in a reactor core using in-core sensors has been an ongoing focus of research… (more)

Subjects/Keywords: Nuclear Engineering; nuclear reactor; flux; uncertainty quantification; reactor physics

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APA (6th Edition):

Kennedy, R. A. (2011). Quantifying Uncertainty in Reactor Flux/Power Distributions. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901

Chicago Manual of Style (16th Edition):

Kennedy, Ryanne Ariel. “Quantifying Uncertainty in Reactor Flux/Power Distributions.” 2011. Doctoral Dissertation, The Ohio State University. Accessed June 18, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901.

MLA Handbook (7th Edition):

Kennedy, Ryanne Ariel. “Quantifying Uncertainty in Reactor Flux/Power Distributions.” 2011. Web. 18 Jun 2019.

Vancouver:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Internet] [Doctoral dissertation]. The Ohio State University; 2011. [cited 2019 Jun 18]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901.

Council of Science Editors:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Doctoral Dissertation]. The Ohio State University; 2011. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901


McMaster University

2. McDonald, Michael H. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.

Degree: MASc, 2011, McMaster University

The supercritical water cooled reactor (SCWR) is a Generation IV reactor concept that features light water coolant in a supercritical state. Canada is developing… (more)

Subjects/Keywords: Reactor physics; supercritical water cooled reactor; fuel; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

McDonald, M. H. (2011). Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11223

Chicago Manual of Style (16th Edition):

McDonald, Michael H. “Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.” 2011. Masters Thesis, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/11223.

MLA Handbook (7th Edition):

McDonald, Michael H. “Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.” 2011. Web. 18 Jun 2019.

Vancouver:

McDonald MH. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/11223.

Council of Science Editors:

McDonald MH. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11223


University of Ontario Institute of Technology

3. Patel, Amin. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.

Degree: 2010, University of Ontario Institute of Technology

 Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several… (more)

Subjects/Keywords: Applied reactor physics; Transport theory; Diffusion theory; CANDU; Nuclear reactor

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APA (6th Edition):

Patel, A. (2010). Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/87

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):

Patel, Amin. “Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.” 2010. Thesis, University of Ontario Institute of Technology. Accessed June 18, 2019. http://hdl.handle.net/10155/87.

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

MLA Handbook (7th Edition):

Patel, Amin. “Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.” 2010. Web. 18 Jun 2019.

Vancouver:

Patel A. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. [Internet] [Thesis]. University of Ontario Institute of Technology; 2010. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/10155/87.

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

Council of Science Editors:

Patel A. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. [Thesis]. University of Ontario Institute of Technology; 2010. Available from: http://hdl.handle.net/10155/87

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

4. Talley, Kemper Dyar. Beta-Delayed Neutron Data and Models for SCALE.

Degree: 2016, University of Tennessee – Knoxville

 Recent advancements in experimental and theoretical nuclear physics have yielded new data and models that more accurately describe the decay of fission products compared to… (more)

Subjects/Keywords: Neutron Emission; Beta Decay; Nuclear Physics; Reactor Physics; Nuclear Data; SCALE; Nuclear; Nuclear Engineering

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APA (6th Edition):

Talley, K. D. (2016). Beta-Delayed Neutron Data and Models for SCALE. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/4170

Chicago Manual of Style (16th Edition):

Talley, Kemper Dyar. “Beta-Delayed Neutron Data and Models for SCALE.” 2016. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed June 18, 2019. https://trace.tennessee.edu/utk_graddiss/4170.

MLA Handbook (7th Edition):

Talley, Kemper Dyar. “Beta-Delayed Neutron Data and Models for SCALE.” 2016. Web. 18 Jun 2019.

Vancouver:

Talley KD. Beta-Delayed Neutron Data and Models for SCALE. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2019 Jun 18]. Available from: https://trace.tennessee.edu/utk_graddiss/4170.

Council of Science Editors:

Talley KD. Beta-Delayed Neutron Data and Models for SCALE. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_graddiss/4170


University of Cambridge

5. Lindley, Benjamin A. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.

Degree: PhD, 2015, University of Cambridge

 Light water reactors (LWRs) are the world’s dominant nuclear reactor system. Uranium (U)-fuelled LWRs produce long-lived transuranic (TRU) isotopes. TRUs can be recycled in LWRs… (more)

Subjects/Keywords: 539.7; Thorium; Light Water Reactor; Plutonium; Transuranic; Reduced-moderation; Nuclear fuel cycle; Reactor physics

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APA (6th Edition):

Lindley, B. A. (2015). The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. (Doctoral Dissertation). University of Cambridge. Retrieved from https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470

Chicago Manual of Style (16th Edition):

Lindley, Benjamin A. “The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.” 2015. Doctoral Dissertation, University of Cambridge. Accessed June 18, 2019. https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470.

MLA Handbook (7th Edition):

Lindley, Benjamin A. “The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.” 2015. Web. 18 Jun 2019.

Vancouver:

Lindley BA. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. [Internet] [Doctoral dissertation]. University of Cambridge; 2015. [cited 2019 Jun 18]. Available from: https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470.

Council of Science Editors:

Lindley BA. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. [Doctoral Dissertation]. University of Cambridge; 2015. Available from: https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470


McMaster University

6. Russell, Liam F. Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit.

Degree: MASc, 2012, McMaster University

When the material or geometry of a reactor varies with time, the neutron flux will respond in the form of a reactor transient. These… (more)

Subjects/Keywords: Monte Carlo; reactor physics; nuclear engineering; stochastic; time-dependent; Geant4; Engineering Physics; Nuclear; Nuclear Engineering; Engineering Physics

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APA (6th Edition):

Russell, L. F. (2012). Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/12657

Chicago Manual of Style (16th Edition):

Russell, Liam F. “Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit.” 2012. Masters Thesis, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/12657.

MLA Handbook (7th Edition):

Russell, Liam F. “Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit.” 2012. Web. 18 Jun 2019.

Vancouver:

Russell LF. Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit. [Internet] [Masters thesis]. McMaster University; 2012. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/12657.

Council of Science Editors:

Russell LF. Simulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkit. [Masters Thesis]. McMaster University; 2012. Available from: http://hdl.handle.net/11375/12657


The Ohio State University

7. Abejon Orzaez, Jorge. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.

Degree: MS, Nuclear Engineering, 2009, The Ohio State University

 The objective of this research is to, based on the original design for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), develop an MCNPX model… (more)

Subjects/Keywords: Engineering; Nuclear Physics; Neutronics; advanced high temperature reactor; criticality

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APA (6th Edition):

Abejon Orzaez, J. (2009). Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558

Chicago Manual of Style (16th Edition):

Abejon Orzaez, Jorge. “Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.” 2009. Masters Thesis, The Ohio State University. Accessed June 18, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.

MLA Handbook (7th Edition):

Abejon Orzaez, Jorge. “Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.” 2009. Web. 18 Jun 2019.

Vancouver:

Abejon Orzaez J. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Jun 18]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.

Council of Science Editors:

Abejon Orzaez J. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. [Masters Thesis]. The Ohio State University; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558


University of Manchester

8. Black, Greg. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.

Degree: Thesis (Eng.D.), 2014, University of Manchester

 The University of Manchester Greg BlackThesis submitted for the degree of Doctor of EngineeringIrradiated Graphite Waste: Analysis and Modelling of Radionuclide Production with a View… (more)

Subjects/Keywords: 621.48; Nuclear Graphite; Radioactive Waste Management; Reactor Physics Modelling; Gamma Spectroscopy

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APA (6th Edition):

Black, G. (2014). Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547

Chicago Manual of Style (16th Edition):

Black, Greg. “Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.” 2014. Doctoral Dissertation, University of Manchester. Accessed June 18, 2019. https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547.

MLA Handbook (7th Edition):

Black, Greg. “Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.” 2014. Web. 18 Jun 2019.

Vancouver:

Black G. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. [Internet] [Doctoral dissertation]. University of Manchester; 2014. [cited 2019 Jun 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547.

Council of Science Editors:

Black G. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. [Doctoral Dissertation]. University of Manchester; 2014. Available from: https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547


McMaster University

9. McEwan, Curtis E. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.

Degree: MASc, 2013, McMaster University

Simulation plays a key role in nuclear reactor safety analysis and being able to assess the accuracy of results obtained by simulation increases their… (more)

Subjects/Keywords: Reactor Physics; Covariance; Uncertainty Analysis; Total Monte Carlo; Dilution; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

McEwan, C. E. (2013). Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/13396

Chicago Manual of Style (16th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Masters Thesis, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/13396.

MLA Handbook (7th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Web. 18 Jun 2019.

Vancouver:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/13396.

Council of Science Editors:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Masters Thesis]. McMaster University; 2013. Available from: http://hdl.handle.net/11375/13396


McMaster University

10. Tan, Andrew. Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code.

Degree: MASc, 2015, McMaster University

The goal of this thesis is to study the transient behaviour of the SLOWPOKE-2 reactor using Monte-Carlo simulations with the G4-STORK code. G4-STORK is a… (more)

Subjects/Keywords: Nuclear Physics; Reactor Physics; Nuclear Engineering; Simulations; Transient; Transient Simulations; GEANT4; G4-STORK; Computational Physics; SLOWPOKE-2

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APA (6th Edition):

Tan, A. (2015). Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/18666

Chicago Manual of Style (16th Edition):

Tan, Andrew. “Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code.” 2015. Masters Thesis, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/18666.

MLA Handbook (7th Edition):

Tan, Andrew. “Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code.” 2015. Web. 18 Jun 2019.

Vancouver:

Tan A. Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code. [Internet] [Masters thesis]. McMaster University; 2015. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/18666.

Council of Science Editors:

Tan A. Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code. [Masters Thesis]. McMaster University; 2015. Available from: http://hdl.handle.net/11375/18666


McMaster University

11. Ball, Matthew R. Uncertainty Analysis In Lattice Reactor Physics Calculations.

Degree: PhD, 2011, McMaster University

Comprehensive sensitivity and uncertainty analysis has been performed for light-water reactor and heavy-water reactor lattices using three techniques; adjoint-based sensitivity analysis, Monte Carlo sampling,… (more)

Subjects/Keywords: nuclear engineering; reactor physics; uncertainty analysis; covariance; cross-sections; resonance self-shielding; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Ball, M. R. (2011). Uncertainty Analysis In Lattice Reactor Physics Calculations. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/11609

Chicago Manual of Style (16th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Doctoral Dissertation, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/11609.

MLA Handbook (7th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Web. 18 Jun 2019.

Vancouver:

Ball MR. Uncertainty Analysis In Lattice Reactor Physics Calculations. [Internet] [Doctoral dissertation]. McMaster University; 2011. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/11609.

Council of Science Editors:

Ball MR. Uncertainty Analysis In Lattice Reactor Physics Calculations. [Doctoral Dissertation]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11609


Virginia Tech

12. Jaffke, Patrick John. Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors.

Degree: PhD, Physics, 2015, Virginia Tech

 In this work, the antineutrino spectrum as specifically generated by nuclear reactors is studied. The topics covered include corrections and higher-order effects in reactor antineutrino… (more)

Subjects/Keywords: Neutrino Physics; Reactor Physics; Spent Nuclear Fuel Correction; Non-linear Correction; Antineutrino Safeguards; Nuclear Non-proliferation

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APA (6th Edition):

Jaffke, P. J. (2015). Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/80031

Chicago Manual of Style (16th Edition):

Jaffke, Patrick John. “Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors.” 2015. Doctoral Dissertation, Virginia Tech. Accessed June 18, 2019. http://hdl.handle.net/10919/80031.

MLA Handbook (7th Edition):

Jaffke, Patrick John. “Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors.” 2015. Web. 18 Jun 2019.

Vancouver:

Jaffke PJ. Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors. [Internet] [Doctoral dissertation]. Virginia Tech; 2015. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/10919/80031.

Council of Science Editors:

Jaffke PJ. Corrections to and Applications of the Antineutrino Spectrum Generated by Nuclear Reactors. [Doctoral Dissertation]. Virginia Tech; 2015. Available from: http://hdl.handle.net/10919/80031


University of California – Irvine

13. Heckmaier, Elizabeth Klara Marie. Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy.

Degree: Physics, 2018, University of California – Irvine

 Since the discovery of the neutrino in 1956, nuclear reactors have played an important role in understanding the properties of beta decay and probing the… (more)

Subjects/Keywords: Nuclear physics and radiation; Particle physics; Beta Spectroscopy; Decay; Detectors; Nuclear; Reactor Antineutrino Anomaly; Weak Interaction

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APA (6th Edition):

Heckmaier, E. K. M. (2018). Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy. (Thesis). University of California – Irvine. Retrieved from http://www.escholarship.org/uc/item/7rd5f743

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):

Heckmaier, Elizabeth Klara Marie. “Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy.” 2018. Thesis, University of California – Irvine. Accessed June 18, 2019. http://www.escholarship.org/uc/item/7rd5f743.

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

MLA Handbook (7th Edition):

Heckmaier, Elizabeth Klara Marie. “Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy.” 2018. Web. 18 Jun 2019.

Vancouver:

Heckmaier EKM. Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy. [Internet] [Thesis]. University of California – Irvine; 2018. [cited 2019 Jun 18]. Available from: http://www.escholarship.org/uc/item/7rd5f743.

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

Council of Science Editors:

Heckmaier EKM. Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy. [Thesis]. University of California – Irvine; 2018. Available from: http://www.escholarship.org/uc/item/7rd5f743

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

14. Serra, André da Silva. Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem.

Degree: PhD, Física, 2012, University of São Paulo

O presente trabalho visa contribuir com o desenvolvimento sistemático de novas metodologias experimentais da medida da reatividade de arranjos físseis subcríticos, utilizando: estatísticas de alta… (more)

Subjects/Keywords: cinética de reatores; estatísticas; física de reatores; nuclear reactors; reactivity; reactor kinetics; reactor physics; reatividade; reatores nucleares; statistics

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APA (6th Edition):

Serra, A. d. S. (2012). Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/43/43134/tde-26032013-121339/ ;

Chicago Manual of Style (16th Edition):

Serra, André da Silva. “Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem.” 2012. Doctoral Dissertation, University of São Paulo. Accessed June 18, 2019. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-26032013-121339/ ;.

MLA Handbook (7th Edition):

Serra, André da Silva. “Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem.” 2012. Web. 18 Jun 2019.

Vancouver:

Serra AdS. Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem. [Internet] [Doctoral dissertation]. University of São Paulo; 2012. [cited 2019 Jun 18]. Available from: http://www.teses.usp.br/teses/disponiveis/43/43134/tde-26032013-121339/ ;.

Council of Science Editors:

Serra AdS. Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem. [Doctoral Dissertation]. University of São Paulo; 2012. Available from: http://www.teses.usp.br/teses/disponiveis/43/43134/tde-26032013-121339/ ;


Texas A&M University

15. Sternat, Matthew Ryan 1982-. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.

Degree: 2012, Texas A&M University

 Pre-detonation technical nuclear forensics techniques for research reactor spent fuel were developed in a collaborative project with Savannah River National Lab ratory. An inverse analysis… (more)

Subjects/Keywords: Attribution; Spent Fuel; Research Reactor; Savannah River National Laboratory; Radiochemical Analysis; Inverse Reactor Physics; Inverse Problems; Nuclear Forensics

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

APA (6th Edition):

Sternat, M. R. 1. (2012). Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148202

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):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Thesis, Texas A&M University. Accessed June 18, 2019. http://hdl.handle.net/1969.1/148202.

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

MLA Handbook (7th Edition):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Web. 18 Jun 2019.

Vancouver:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/1969.1/148202.

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

Council of Science Editors:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148202

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


Missouri University of Science and Technology

16. Compton, William Kirby. Impact of configuration variations on small modular reactor core performance.

Degree: M.S. in Nuclear Engineering, Nuclear Engineering, Missouri University of Science and Technology

  "One of the most promising new reactor designs is the Small Modular Reactor (SMR). These reactors, which operate under 300 MWe, will help bring… (more)

Subjects/Keywords: MCNP; Reactor Physics; Small Modular Reactor; Nuclear Engineering

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

APA (6th Edition):

Compton, W. K. (n.d.). Impact of configuration variations on small modular reactor core performance. (Masters Thesis). Missouri University of Science and Technology. Retrieved from http://scholarsmine.mst.edu/masters_theses/7391

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Chicago Manual of Style (16th Edition):

Compton, William Kirby. “Impact of configuration variations on small modular reactor core performance.” Masters Thesis, Missouri University of Science and Technology. Accessed June 18, 2019. http://scholarsmine.mst.edu/masters_theses/7391.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

MLA Handbook (7th Edition):

Compton, William Kirby. “Impact of configuration variations on small modular reactor core performance.” Web. 18 Jun 2019.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Vancouver:

Compton WK. Impact of configuration variations on small modular reactor core performance. [Internet] [Masters thesis]. Missouri University of Science and Technology; [cited 2019 Jun 18]. Available from: http://scholarsmine.mst.edu/masters_theses/7391.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Council of Science Editors:

Compton WK. Impact of configuration variations on small modular reactor core performance. [Masters Thesis]. Missouri University of Science and Technology; Available from: http://scholarsmine.mst.edu/masters_theses/7391

Note: this citation may be lacking information needed for this citation format:
No year of publication.


McMaster University

17. Younan, Simon. Comparative study of accident-tolerant fuel for a CANDU lattice.

Degree: MASc, 2017, McMaster University

McMaster University MASTER OF APPLIED SCIENCES (2017) Hamilton, Ontario (Engineering Physics) TITLE: Comparative study of accident-tolerant fuel for a CANDU lattice AUTHOR: Simon Younan, B.Eng.… (more)

Subjects/Keywords: nuclear engineering; reactor physics; CANDU; accident-tolerant fuel; Serpent 2; Monte Carlo; accident-tolerant cladding

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APA (6th Edition):

Younan, S. (2017). Comparative study of accident-tolerant fuel for a CANDU lattice. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/22194

Chicago Manual of Style (16th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Masters Thesis, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/22194.

MLA Handbook (7th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Web. 18 Jun 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/22194.

Council of Science Editors:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22194


McMaster University

18. Sharpe, Jason. Innovative Analysis Techniques for Canadian SCWR Neutronics.

Degree: PhD, 2017, McMaster University

Knowledge of the effects of nuclear data uncertainties and physics approximations is crucial for the development, design, operation, and accident mitigation, of nuclear power plants.… (more)

Subjects/Keywords: physics; neutronics; engineering; nuclear; scwr; canadian; reactor; super; critical; water-cooled; diffusion; experiment; transport; technique

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APA (6th Edition):

Sharpe, J. (2017). Innovative Analysis Techniques for Canadian SCWR Neutronics. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/22064

Chicago Manual of Style (16th Edition):

Sharpe, Jason. “Innovative Analysis Techniques for Canadian SCWR Neutronics.” 2017. Doctoral Dissertation, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/22064.

MLA Handbook (7th Edition):

Sharpe, Jason. “Innovative Analysis Techniques for Canadian SCWR Neutronics.” 2017. Web. 18 Jun 2019.

Vancouver:

Sharpe J. Innovative Analysis Techniques for Canadian SCWR Neutronics. [Internet] [Doctoral dissertation]. McMaster University; 2017. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/22064.

Council of Science Editors:

Sharpe J. Innovative Analysis Techniques for Canadian SCWR Neutronics. [Doctoral Dissertation]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22064

19. Rossi, Pedro Carlos Russo. Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte.

Degree: PhD, Tecnologia Nuclear - Reatores, 2011, University of São Paulo

Neste trabalho apresentamos um estudo das reações nucleares de alta energia que são fundamentais na definição do termo fonte dos reatores nucleares subcríticos acionados por… (more)

Subjects/Keywords: accelerator driven system; física de reatores; física nuclear; nuclear multifragmentation; nuclear physics; nuclear reactions; reações nucleares; reactor physics; reatores subcríticos acionados por fonte; spallation; spallation source

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APA (6th Edition):

Rossi, P. C. R. (2011). Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-132603/ ;

Chicago Manual of Style (16th Edition):

Rossi, Pedro Carlos Russo. “Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte.” 2011. Doctoral Dissertation, University of São Paulo. Accessed June 18, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-132603/ ;.

MLA Handbook (7th Edition):

Rossi, Pedro Carlos Russo. “Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte.” 2011. Web. 18 Jun 2019.

Vancouver:

Rossi PCR. Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte. [Internet] [Doctoral dissertation]. University of São Paulo; 2011. [cited 2019 Jun 18]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-132603/ ;.

Council of Science Editors:

Rossi PCR. Reações nucleares de alta energia (\" Spallation\") e sua aplicação em cálculo de sistemas nucleares acionados por  Fonte. [Doctoral Dissertation]. University of São Paulo; 2011. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-132603/ ;


University of Tennessee – Knoxville

20. Hernandez Noyola, Hermilo. Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors.

Degree: 2010, University of Tennessee – Knoxville

 A generalized software capability has been developed for the pin-wise loading optimization of light water reactor (LWR) fuel lattices with the enhanced flexibility of control… (more)

Subjects/Keywords: Minor Actinides Recycling; Light Water Reactors; Lattice optimization; Simulated Annealing; Lattice to core coupling; Nuclear Reactor Physics; Computational Engineering; Nuclear Engineering

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APA (6th Edition):

Hernandez Noyola, H. (2010). Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/886

Chicago Manual of Style (16th Edition):

Hernandez Noyola, Hermilo. “Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors.” 2010. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed June 18, 2019. https://trace.tennessee.edu/utk_graddiss/886.

MLA Handbook (7th Edition):

Hernandez Noyola, Hermilo. “Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors.” 2010. Web. 18 Jun 2019.

Vancouver:

Hernandez Noyola H. Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2010. [cited 2019 Jun 18]. Available from: https://trace.tennessee.edu/utk_graddiss/886.

Council of Science Editors:

Hernandez Noyola H. Pin-Wise Loading Optimization and Lattice–to-Core Coupling for Isotopic Management in Light Water Reactors. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2010. Available from: https://trace.tennessee.edu/utk_graddiss/886


University of Florida

21. Rolison, Lucas. Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster.

Degree: 2013, University of Florida

 High-performance computing has become a necessary tool in the field of science and engineering. The problems faced in the field of nuclear engineering represent one… (more)

Subjects/Keywords: Computer memory; Distributed memory; Ethernet; Libraries; Multiprocessors; Nuclear engineering; Reactor physics; Run time; Scalability; Water quality; High performance computing; Nuclear engineering

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APA (6th Edition):

Rolison, L. (2013). Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster. (Thesis). University of Florida. Retrieved from http://ufdc.ufl.edu/AA00057348

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):

Rolison, Lucas. “Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster.” 2013. Thesis, University of Florida. Accessed June 18, 2019. http://ufdc.ufl.edu/AA00057348.

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

MLA Handbook (7th Edition):

Rolison, Lucas. “Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster.” 2013. Web. 18 Jun 2019.

Vancouver:

Rolison L. Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster. [Internet] [Thesis]. University of Florida; 2013. [cited 2019 Jun 18]. Available from: http://ufdc.ufl.edu/AA00057348.

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

Council of Science Editors:

Rolison L. Testing of SERPENT Scalability on the University of Florida High-Performance Computing Cluster. [Thesis]. University of Florida; 2013. Available from: http://ufdc.ufl.edu/AA00057348

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

22. Santos, Diogo Feliciano dos. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2015, University of São Paulo

Os experimentos realizados e apresentados nesta dissertação resultaram na caracterização neutrônica de núcleos na configuração cilíndrica com 30 varetas combustíveis de diâmetro com um espaço,… (more)

Subjects/Keywords: análise por ativação neutrônica; espectrometria gama; física de reator nuclear; fluxo de nêutrons; gamma spectrometry; neutron activation analysis; neutron flux; nuclear reaction rate; nuclear reactor physics; taxa de reação nuclear

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APA (6th Edition):

Santos, D. F. d. (2015). Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;

Chicago Manual of Style (16th Edition):

Santos, Diogo Feliciano dos. “Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.” 2015. Masters Thesis, University of São Paulo. Accessed June 18, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;.

MLA Handbook (7th Edition):

Santos, Diogo Feliciano dos. “Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.” 2015. Web. 18 Jun 2019.

Vancouver:

Santos DFd. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. [Internet] [Masters thesis]. University of São Paulo; 2015. [cited 2019 Jun 18]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;.

Council of Science Editors:

Santos DFd. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. [Masters Thesis]. University of São Paulo; 2015. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;


Missouri University of Science and Technology

23. Jaradat, Safwan Qasim Mohammad. Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle.

Degree: PhD, Nuclear Engineering, Missouri University of Science and Technology

  "Molten salt reactor (MSR) is one of six reactors selected by the Generation IV International Forum (GIF). The liquid fluoride thorium reactor (LFTR) is… (more)

Subjects/Keywords: LFTR; Liquid fluoride thorium reactor; Molten salt reactor; MSR; Nuclear reactor physics; Thorium fuel cycle; Nuclear Engineering

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APA (6th Edition):

Jaradat, S. Q. M. (n.d.). Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle. (Doctoral Dissertation). Missouri University of Science and Technology. Retrieved from http://scholarsmine.mst.edu/doctoral_dissertations/2448

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Chicago Manual of Style (16th Edition):

Jaradat, Safwan Qasim Mohammad. “Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle.” Doctoral Dissertation, Missouri University of Science and Technology. Accessed June 18, 2019. http://scholarsmine.mst.edu/doctoral_dissertations/2448.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

MLA Handbook (7th Edition):

Jaradat, Safwan Qasim Mohammad. “Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle.” Web. 18 Jun 2019.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Vancouver:

Jaradat SQM. Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle. [Internet] [Doctoral dissertation]. Missouri University of Science and Technology; [cited 2019 Jun 18]. Available from: http://scholarsmine.mst.edu/doctoral_dissertations/2448.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Council of Science Editors:

Jaradat SQM. Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle. [Doctoral Dissertation]. Missouri University of Science and Technology; Available from: http://scholarsmine.mst.edu/doctoral_dissertations/2448

Note: this citation may be lacking information needed for this citation format:
No year of publication.


The Ohio State University

24. Reinke, Benjamin T. Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool.

Degree: MS, Nuclear Engineering, 2015, The Ohio State University

 A Cryogenic Irradiation Facility (CRIF) has been designed, fabricated, and tested for use in the pool of the Ohio State University Research Reactor (OSURR). This… (more)

Subjects/Keywords: Materials Science; Nuclear Physics; Nuclear Engineering; radiation; cryogenic irradiation facility; cryogenic, radiation damage; defect generation; electronic; optical; CRIF; MCNP; OSURR; research reactor; irradiation facility, low temperature annealing

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APA (6th Edition):

Reinke, B. T. (2015). Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576

Chicago Manual of Style (16th Edition):

Reinke, Benjamin T. “Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool.” 2015. Masters Thesis, The Ohio State University. Accessed June 18, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576.

MLA Handbook (7th Edition):

Reinke, Benjamin T. “Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool.” 2015. Web. 18 Jun 2019.

Vancouver:

Reinke BT. Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool. [Internet] [Masters thesis]. The Ohio State University; 2015. [cited 2019 Jun 18]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576.

Council of Science Editors:

Reinke BT. Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool. [Masters Thesis]. The Ohio State University; 2015. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576


McMaster University

25. Moghrabi, Ahmad. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.

Degree: PhD, 2018, McMaster University

The Generation IV International Forum (GIF) has initiated an international collaboration for the research and development of the Generation IV future nuclear energy systems. The… (more)

Subjects/Keywords: Generation IV nuclear reactor; Canadian PT-SCWR; Advanced nuclear Energy system; Lattice physics phenomena; Energy group structure optimization; SCALE code; Uncertainty Analysis; Sensitivity Analysis; Transport Calcuations; Optimization and algorithm

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APA (6th Edition):

Moghrabi, A. (2018). INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/22886

Chicago Manual of Style (16th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Doctoral Dissertation, McMaster University. Accessed June 18, 2019. http://hdl.handle.net/11375/22886.

MLA Handbook (7th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Web. 18 Jun 2019.

Vancouver:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/11375/22886.

Council of Science Editors:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Doctoral Dissertation]. McMaster University; 2018. Available from: http://hdl.handle.net/11375/22886


North Carolina State University

26. Wieselquist, William Adam. The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE.

Degree: MS, Nuclear Engineering, 2005, North Carolina State University

 In support of the need for better design and evaluation tools for reactor-based transmutation systems we have upgraded NESTLE, the 2/4 energy group thermal reactor(more)

Subjects/Keywords: sensitivity analysis; nuclear engineering; nuclear data; NESTLE; reactor physics; uncertainty propagation

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APA (6th Edition):

Wieselquist, W. A. (2005). The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE. (Thesis). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/1861

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):

Wieselquist, William Adam. “The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE.” 2005. Thesis, North Carolina State University. Accessed June 18, 2019. http://www.lib.ncsu.edu/resolver/1840.16/1861.

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

MLA Handbook (7th Edition):

Wieselquist, William Adam. “The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE.” 2005. Web. 18 Jun 2019.

Vancouver:

Wieselquist WA. The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE. [Internet] [Thesis]. North Carolina State University; 2005. [cited 2019 Jun 18]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/1861.

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

Council of Science Editors:

Wieselquist WA. The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE. [Thesis]. North Carolina State University; 2005. Available from: http://www.lib.ncsu.edu/resolver/1840.16/1861

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

27. Huang, Lloyd Michael. Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning.

Degree: PhD, Mechanical Engineering, 2017, Georgia Tech

 The Liquid Salt Cooled Reactor (LSCR) is a graphite moderated and liquid salt cooled reactor The LSCR is designed with the intention of providing superior… (more)

Subjects/Keywords: Neutronics; Optimization; Machine learning; Neural networks; Reactor physics; Advanced high temperature reactor; Advanced reactor; Nuclear reactor; Monte Carlo

reactor physics and statistics problem. AHTR Design Background The AHTR is a 3400 MWth high… …analyzed in Chapter 5. Finally the two sides of the research, reactor physics and statistics, are… …modeling methodology. Physics surrogate model is generated with Artificial Neural Network (… …106 xv LIST OF ABBREVIATIONS AHTR Advanced High Temperature Reactor TRISO… …Tristructural-Isotropic Fuel HTR High Temperature Reactor (Gas cooled) CHM Carbon-to… 

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APA (6th Edition):

Huang, L. M. (2017). Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58712

Chicago Manual of Style (16th Edition):

Huang, Lloyd Michael. “Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning.” 2017. Doctoral Dissertation, Georgia Tech. Accessed June 18, 2019. http://hdl.handle.net/1853/58712.

MLA Handbook (7th Edition):

Huang, Lloyd Michael. “Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning.” 2017. Web. 18 Jun 2019.

Vancouver:

Huang LM. Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning. [Internet] [Doctoral dissertation]. Georgia Tech; 2017. [cited 2019 Jun 18]. Available from: http://hdl.handle.net/1853/58712.

Council of Science Editors:

Huang LM. Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning. [Doctoral Dissertation]. Georgia Tech; 2017. Available from: http://hdl.handle.net/1853/58712

28. Laureau, Axel. Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters.

Degree: Docteur es, Mécanique des fluides, procédés, énergétique, 2015, Grenoble Alpes

Le travail de cette thèse porte sur le développement de modèles neutroniques innovants pour le couplage avec la thermohydraulique, associant précision et temps de calcul… (more)

Subjects/Keywords: Réacteur nucléaire; Modèles neutroniques; Paramètres cinétiques; Couplage multi-physique; Transitoire; MSFR; Nuclear reactor; Neutronic models; Kinetic parameters; Multi-physics coupling; Transient; MSFR; 620

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

APA (6th Edition):

Laureau, A. (2015). Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters. (Doctoral Dissertation). Grenoble Alpes. Retrieved from http://www.theses.fr/2015GREAI064

Chicago Manual of Style (16th Edition):

Laureau, Axel. “Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters.” 2015. Doctoral Dissertation, Grenoble Alpes. Accessed June 18, 2019. http://www.theses.fr/2015GREAI064.

MLA Handbook (7th Edition):

Laureau, Axel. “Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters.” 2015. Web. 18 Jun 2019.

Vancouver:

Laureau A. Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters. [Internet] [Doctoral dissertation]. Grenoble Alpes; 2015. [cited 2019 Jun 18]. Available from: http://www.theses.fr/2015GREAI064.

Council of Science Editors:

Laureau A. Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters. [Doctoral Dissertation]. Grenoble Alpes; 2015. Available from: http://www.theses.fr/2015GREAI064


Brunel University

29. Caulton, Graham K. The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans.

Degree: PhD, 1966, Brunel University

 The development of magnox fuel cans at the Heston Laboratories of A.P.C. Ltd. required a non-contact method of measuring fuel can temperature during heat transfer… (more)

Subjects/Keywords: 621.31; Electromechanical Devices; Nuclear Reactor Technology; Optics; Physics, general; Thermodynamics

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APA (6th Edition):

Caulton, G. K. (1966). The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans. (Doctoral Dissertation). Brunel University. Retrieved from http://bura.brunel.ac.uk/handle/2438/414 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665

Chicago Manual of Style (16th Edition):

Caulton, Graham K. “The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans.” 1966. Doctoral Dissertation, Brunel University. Accessed June 18, 2019. http://bura.brunel.ac.uk/handle/2438/414 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665.

MLA Handbook (7th Edition):

Caulton, Graham K. “The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans.” 1966. Web. 18 Jun 2019.

Vancouver:

Caulton GK. The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans. [Internet] [Doctoral dissertation]. Brunel University; 1966. [cited 2019 Jun 18]. Available from: http://bura.brunel.ac.uk/handle/2438/414 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665.

Council of Science Editors:

Caulton GK. The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans. [Doctoral Dissertation]. Brunel University; 1966. Available from: http://bura.brunel.ac.uk/handle/2438/414 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665

30. Black, Greg. Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal.

Degree: 2014, University of Manchester

 The University of Manchester Greg BlackThesis submitted for the degree of Doctor of EngineeringIrradiated Graphite Waste: Analysis and Modelling of Radionuclide Production with a View… (more)

Subjects/Keywords: Nuclear Graphite; Radioactive Waste Management; Reactor Physics Modelling; Gamma Spectroscopy

reactor physics code WIMS, and radiation transport code MCBEND. Activation calculations have… …interest in the core. This can be simulated using a suitable reactor physics code such as MCBEND… …113 Figure 40: Comparison of EAF-2007, JEFF-3.0/A and TENDL-2009 nuclear data for the 13 C… …Figure 44: Chargepan map of Wylfa reactor 1. Each segment represents a single chargepan which… …139 Figure 54: MCBEND quadrant model of the Oldbury reactor 2 with the installed sample… 

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

APA (6th Edition):

Black, G. (2014). Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:227557

Chicago Manual of Style (16th Edition):

Black, Greg. “Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal.” 2014. Doctoral Dissertation, University of Manchester. Accessed June 18, 2019. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:227557.

MLA Handbook (7th Edition):

Black, Greg. “Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal.” 2014. Web. 18 Jun 2019.

Vancouver:

Black G. Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal. [Internet] [Doctoral dissertation]. University of Manchester; 2014. [cited 2019 Jun 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:227557.

Council of Science Editors:

Black G. Irradiated Graphite Waste: Analysis and Modelling of Radionuclide Production With a View to Long Term Disposal. [Doctoral Dissertation]. University of Manchester; 2014. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:227557

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