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You searched for subject:(Reactor physics). Showing records 1 – 30 of 79 total matches.

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University of Ontario Institute of Technology

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

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 February 16, 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. 16 Feb 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 Feb 16]. 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


The Ohio State University

2. 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 February 16, 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. 16 Feb 2019.

Vancouver:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Internet] [Doctoral dissertation]. The Ohio State University; 2011. [cited 2019 Feb 16]. 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


Georgia Tech

3. Abou Jaoude, Abdalla. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.

Degree: PhD, Mechanical Engineering, 2017, Georgia Tech

 Long-lived fast reactors have been suggested as an effective way of spreading nuclear energy to new countries. These small reactors can be produced at centralized… (more)

Subjects/Keywords: Reactor physics; Proliferation resistance; Mixed-spectrum reactors; Reactor design; Safety evaluation

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APA (6th Edition):

Abou Jaoude, A. (2017). Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59275

Chicago Manual of Style (16th Edition):

Abou Jaoude, Abdalla. “Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.” 2017. Doctoral Dissertation, Georgia Tech. Accessed February 16, 2019. http://hdl.handle.net/1853/59275.

MLA Handbook (7th Edition):

Abou Jaoude, Abdalla. “Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.” 2017. Web. 16 Feb 2019.

Vancouver:

Abou Jaoude A. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. [Internet] [Doctoral dissertation]. Georgia Tech; 2017. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1853/59275.

Council of Science Editors:

Abou Jaoude A. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. [Doctoral Dissertation]. Georgia Tech; 2017. Available from: http://hdl.handle.net/1853/59275


McMaster University

4. 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 February 16, 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. 16 Feb 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 Feb 16]. 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

5. Mohapatra, Subhramanyu. Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors.

Degree: 2016, University of Ontario Institute of Technology

 To avoid the computational effort associated with full-core neutron transport calculations, full-core neutronics calculations for Pressurized Heavy-Water Reactors (PHWRs) are usually performed in diffusion theory… (more)

Subjects/Keywords: Applied reactor physics; Superhomogenization; PHWR; SPH factors

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APA (6th Edition):

Mohapatra, S. (2016). Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/740

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):

Mohapatra, Subhramanyu. “Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors.” 2016. Thesis, University of Ontario Institute of Technology. Accessed February 16, 2019. http://hdl.handle.net/10155/740.

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

MLA Handbook (7th Edition):

Mohapatra, Subhramanyu. “Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors.” 2016. Web. 16 Feb 2019.

Vancouver:

Mohapatra S. Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/10155/740.

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

Council of Science Editors:

Mohapatra S. Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors. [Thesis]. University of Ontario Institute of Technology; 2016. Available from: http://hdl.handle.net/10155/740

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


Texas A&M University

6. Kitcher, Evans Damenortey. Xenon Induced Power Oscillations in a Generic Small Modular Reactor.

Degree: 2016, Texas A&M University

 As world demand for energy continues to grow at unprecedented rates, the world energy portfolio of the future will inevitably include a nuclear energy contribution.… (more)

Subjects/Keywords: Xenon Oscillations; Small Modular Reactor; Multi-physics

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APA (6th Edition):

Kitcher, E. D. (2016). Xenon Induced Power Oscillations in a Generic Small Modular Reactor. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/157767

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):

Kitcher, Evans Damenortey. “Xenon Induced Power Oscillations in a Generic Small Modular Reactor.” 2016. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/157767.

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

MLA Handbook (7th Edition):

Kitcher, Evans Damenortey. “Xenon Induced Power Oscillations in a Generic Small Modular Reactor.” 2016. Web. 16 Feb 2019.

Vancouver:

Kitcher ED. Xenon Induced Power Oscillations in a Generic Small Modular Reactor. [Internet] [Thesis]. Texas A&M University; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/157767.

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

Council of Science Editors:

Kitcher ED. Xenon Induced Power Oscillations in a Generic Small Modular Reactor. [Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/157767

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


University of Colorado

7. Vasiliou, AnGayle Konstance. Thermochemical Conversion of Biomass: A Molecular Viewpoint.

Degree: PhD, Chemistry & Biochemistry, 2011, University of Colorado

  This dissertation describes experiments performed to study the thermal decomposition of biomass from a molecular viewpoint. The structure of biomass consists of three major… (more)

Subjects/Keywords: biomass; decomposition; reactor; thermal; Physical Chemistry; Physics

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APA (6th Edition):

Vasiliou, A. K. (2011). Thermochemical Conversion of Biomass: A Molecular Viewpoint. (Doctoral Dissertation). University of Colorado. Retrieved from http://scholar.colorado.edu/chem_gradetds/53

Chicago Manual of Style (16th Edition):

Vasiliou, AnGayle Konstance. “Thermochemical Conversion of Biomass: A Molecular Viewpoint.” 2011. Doctoral Dissertation, University of Colorado. Accessed February 16, 2019. http://scholar.colorado.edu/chem_gradetds/53.

MLA Handbook (7th Edition):

Vasiliou, AnGayle Konstance. “Thermochemical Conversion of Biomass: A Molecular Viewpoint.” 2011. Web. 16 Feb 2019.

Vancouver:

Vasiliou AK. Thermochemical Conversion of Biomass: A Molecular Viewpoint. [Internet] [Doctoral dissertation]. University of Colorado; 2011. [cited 2019 Feb 16]. Available from: http://scholar.colorado.edu/chem_gradetds/53.

Council of Science Editors:

Vasiliou AK. Thermochemical Conversion of Biomass: A Molecular Viewpoint. [Doctoral Dissertation]. University of Colorado; 2011. Available from: http://scholar.colorado.edu/chem_gradetds/53


Georgia Tech

8. Remley, Kyle E. Development of methods for high performance computing applications of the deterministic stage of comet calculations.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The Coarse Mesh Radiation Transport (COMET) method is a reactor physics method and code that has been used to solve whole core reactor eigenvalue and… (more)

Subjects/Keywords: Coarse mesh transport; Parallel computing; Reactor physics

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APA (6th Edition):

Remley, K. E. (2016). Development of methods for high performance computing applications of the deterministic stage of comet calculations. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58610

Chicago Manual of Style (16th Edition):

Remley, Kyle E. “Development of methods for high performance computing applications of the deterministic stage of comet calculations.” 2016. Doctoral Dissertation, Georgia Tech. Accessed February 16, 2019. http://hdl.handle.net/1853/58610.

MLA Handbook (7th Edition):

Remley, Kyle E. “Development of methods for high performance computing applications of the deterministic stage of comet calculations.” 2016. Web. 16 Feb 2019.

Vancouver:

Remley KE. Development of methods for high performance computing applications of the deterministic stage of comet calculations. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1853/58610.

Council of Science Editors:

Remley KE. Development of methods for high performance computing applications of the deterministic stage of comet calculations. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/58610


Oregon State University

9. 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 16, 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. 16 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 16]. 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


University of Ontario Institute of Technology

10. Ferguson, Thomas. Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model.

Degree: 2018, University of Ontario Institute of Technology

 Superhomogenization (SPH) has gained interest in the industry as a possible method to overcome the inherent limitations of standard homogenization (SH) for full nuclearreactor-core neutronics… (more)

Subjects/Keywords: Applied reactor physics; Superhomogenization; SPH factors; PHWR

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APA (6th Edition):

Ferguson, T. (2018). Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/940

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):

Ferguson, Thomas. “Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model.” 2018. Thesis, University of Ontario Institute of Technology. Accessed February 16, 2019. http://hdl.handle.net/10155/940.

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

MLA Handbook (7th Edition):

Ferguson, Thomas. “Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model.” 2018. Web. 16 Feb 2019.

Vancouver:

Ferguson T. Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model. [Internet] [Thesis]. University of Ontario Institute of Technology; 2018. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/10155/940.

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

Council of Science Editors:

Ferguson T. Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model. [Thesis]. University of Ontario Institute of Technology; 2018. Available from: http://hdl.handle.net/10155/940

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


University of Cambridge

11. 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 February 16, 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. 16 Feb 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 Feb 16]. 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

12. Berggren, Alexander. Development of a Mobile Reactor for Large Scale Water Treatment.

Degree: Physics, 2019, Umeå University

  Water pollution is one of many environmental problems that currently exists and inadequate treatment of industrial wastewater is contributing to further pollution. SpinChem AB's… (more)

Subjects/Keywords: Water treatment; Mobile reactor; Autopilot; Rotating Bed Reactor; Other Physics Topics; Annan fysik

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APA (6th Edition):

Berggren, A. (2019). Development of a Mobile Reactor for Large Scale Water Treatment. (Thesis). Umeå University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:umu:diva-155584

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):

Berggren, Alexander. “Development of a Mobile Reactor for Large Scale Water Treatment.” 2019. Thesis, Umeå University. Accessed February 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:umu:diva-155584.

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

MLA Handbook (7th Edition):

Berggren, Alexander. “Development of a Mobile Reactor for Large Scale Water Treatment.” 2019. Web. 16 Feb 2019.

Vancouver:

Berggren A. Development of a Mobile Reactor for Large Scale Water Treatment. [Internet] [Thesis]. Umeå University; 2019. [cited 2019 Feb 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:umu:diva-155584.

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

Council of Science Editors:

Berggren A. Development of a Mobile Reactor for Large Scale Water Treatment. [Thesis]. Umeå University; 2019. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:umu:diva-155584

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


KTH

13. Luszczek, Karol. Validation and Benchmarking of Westinghouse BWR lattice physics methods.

Degree: Reactor Technology, 2015, KTH

  A lattice physics code is a vital tool, forming a base of reactor coreanalysis. It enables the neutronic properties of the fuel assembly to… (more)

Subjects/Keywords: Serpent; HELIOS; lattice physics; benchmarking; Monte Carlo; neutronics; reactor physics

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APA (6th Edition):

Luszczek, K. (2015). Validation and Benchmarking of Westinghouse BWR lattice physics methods. (Thesis). KTH. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-180563

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):

Luszczek, Karol. “Validation and Benchmarking of Westinghouse BWR lattice physics methods.” 2015. Thesis, KTH. Accessed February 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-180563.

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

MLA Handbook (7th Edition):

Luszczek, Karol. “Validation and Benchmarking of Westinghouse BWR lattice physics methods.” 2015. Web. 16 Feb 2019.

Vancouver:

Luszczek K. Validation and Benchmarking of Westinghouse BWR lattice physics methods. [Internet] [Thesis]. KTH; 2015. [cited 2019 Feb 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-180563.

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

Council of Science Editors:

Luszczek K. Validation and Benchmarking of Westinghouse BWR lattice physics methods. [Thesis]. KTH; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-180563

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


University of Ontario Institute of Technology

14. Carisse, Katarzyna. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.

Degree: 2014, University of Ontario Institute of Technology

 The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the… (more)

Subjects/Keywords: Applied reactor physics; Advanced homogenization; CANDU; PT-SCWR

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APA (6th Edition):

Carisse, K. (2014). Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/458

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):

Carisse, Katarzyna. “Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.” 2014. Thesis, University of Ontario Institute of Technology. Accessed February 16, 2019. http://hdl.handle.net/10155/458.

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

MLA Handbook (7th Edition):

Carisse, Katarzyna. “Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.” 2014. Web. 16 Feb 2019.

Vancouver:

Carisse K. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. [Internet] [Thesis]. University of Ontario Institute of Technology; 2014. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/10155/458.

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

Council of Science Editors:

Carisse K. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. [Thesis]. University of Ontario Institute of Technology; 2014. Available from: http://hdl.handle.net/10155/458

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

15. Domingos, Douglas Borges. Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB.

Degree: PhD, Tecnologia Nuclear - Reatores, 2014, University of São Paulo

Neste trabalho foi realizado uma comparação entre três tipos de alvos (UAl2-Al, U-Ni cilíndrico e U-Ni placa) para a produção de 99Mo por fissão do… (more)

Subjects/Keywords: física de reatores; radiofármacos; radiopharmaceuticals; reactor physics; termo-hidráulica; thermo-hydraulic

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

APA (6th Edition):

Domingos, D. B. (2014). Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-17122014-133601/ ;

Chicago Manual of Style (16th Edition):

Domingos, Douglas Borges. “Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB.” 2014. Doctoral Dissertation, University of São Paulo. Accessed February 16, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-17122014-133601/ ;.

MLA Handbook (7th Edition):

Domingos, Douglas Borges. “Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB.” 2014. Web. 16 Feb 2019.

Vancouver:

Domingos DB. Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB. [Internet] [Doctoral dissertation]. University of São Paulo; 2014. [cited 2019 Feb 16]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-17122014-133601/ ;.

Council of Science Editors:

Domingos DB. Análises neutrônica e termo-hidráulica de dispositivos para irradiação de alvos tipo LEU de UAlx-Al e U-Ni para produção de Mo-99 nos reatores IEA-R1 e RMB. [Doctoral Dissertation]. University of São Paulo; 2014. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-17122014-133601/ ;


The Ohio State University

16. 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 February 16, 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. 16 Feb 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 Feb 16]. 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


Georgia Tech

17. Keller, Steven Ede. Flux-limited Diffusion Coefficient Applied to Reactor Analysis.

Degree: PhD, Nuclear Engineering, 2007, Georgia Tech

 A new definition of the diffusion coefficient for use in reactor physics calculations is evaluated in this thesis. It is based on naturally flux-limited diffusion… (more)

Subjects/Keywords: Transport cross section; Reactor physics

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APA (6th Edition):

Keller, S. E. (2007). Flux-limited Diffusion Coefficient Applied to Reactor Analysis. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/16126

Chicago Manual of Style (16th Edition):

Keller, Steven Ede. “Flux-limited Diffusion Coefficient Applied to Reactor Analysis.” 2007. Doctoral Dissertation, Georgia Tech. Accessed February 16, 2019. http://hdl.handle.net/1853/16126.

MLA Handbook (7th Edition):

Keller, Steven Ede. “Flux-limited Diffusion Coefficient Applied to Reactor Analysis.” 2007. Web. 16 Feb 2019.

Vancouver:

Keller SE. Flux-limited Diffusion Coefficient Applied to Reactor Analysis. [Internet] [Doctoral dissertation]. Georgia Tech; 2007. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1853/16126.

Council of Science Editors:

Keller SE. Flux-limited Diffusion Coefficient Applied to Reactor Analysis. [Doctoral Dissertation]. Georgia Tech; 2007. Available from: http://hdl.handle.net/1853/16126


University of Manchester

18. 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 February 16, 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. 16 Feb 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 Feb 16]. 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


Georgia Tech

19. Kooreman, Gabriel. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The neutron transport equation often is homogenized in order to simplify its solution procedure in some manner or another. There exist many methods for homogenizing… (more)

Subjects/Keywords: Neutron transport; Homogenization; Diffusion; Eigenvalue calculation; Reactor physics

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

APA (6th Edition):

Kooreman, G. (2016). Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59134

Chicago Manual of Style (16th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Doctoral Dissertation, Georgia Tech. Accessed February 16, 2019. http://hdl.handle.net/1853/59134.

MLA Handbook (7th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Web. 16 Feb 2019.

Vancouver:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1853/59134.

Council of Science Editors:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/59134


University of Illinois – Urbana-Champaign

20. McKenzie, George. Modern Rossi alpha measurements.

Degree: MS, 5183, 2015, University of Illinois – Urbana-Champaign

 The Rossi-α method determines the prompt neutron decay constant in a nuclear fissioning system at or near delayed critical. Knowledge of the prompt neutron decay… (more)

Subjects/Keywords: Reactor Physics; Rossi Alpha; Zeus Experiment; Neutron Measurements

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APA (6th Edition):

McKenzie, G. (2015). Modern Rossi alpha measurements. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/72834

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):

McKenzie, George. “Modern Rossi alpha measurements.” 2015. Thesis, University of Illinois – Urbana-Champaign. Accessed February 16, 2019. http://hdl.handle.net/2142/72834.

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

MLA Handbook (7th Edition):

McKenzie, George. “Modern Rossi alpha measurements.” 2015. Web. 16 Feb 2019.

Vancouver:

McKenzie G. Modern Rossi alpha measurements. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2015. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/2142/72834.

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

Council of Science Editors:

McKenzie G. Modern Rossi alpha measurements. [Thesis]. University of Illinois – Urbana-Champaign; 2015. Available from: http://hdl.handle.net/2142/72834

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


North Carolina State University

21. Hiruta, Hikaru. Advanced Computational Methodology for Full-Core Neutronics Calculations.

Degree: PhD, Nuclear Engineering, 2004, North Carolina State University

 The modern computational methodology for reactor physics calculations is based on single–assembly transport calculations with reflective boundary conditions that generate homogenized few–group data, and core–level… (more)

Subjects/Keywords: Reactor Physics; Neutron Transport

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APA (6th Edition):

Hiruta, H. (2004). Advanced Computational Methodology for Full-Core Neutronics Calculations. (Doctoral Dissertation). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/5463

Chicago Manual of Style (16th Edition):

Hiruta, Hikaru. “Advanced Computational Methodology for Full-Core Neutronics Calculations.” 2004. Doctoral Dissertation, North Carolina State University. Accessed February 16, 2019. http://www.lib.ncsu.edu/resolver/1840.16/5463.

MLA Handbook (7th Edition):

Hiruta, Hikaru. “Advanced Computational Methodology for Full-Core Neutronics Calculations.” 2004. Web. 16 Feb 2019.

Vancouver:

Hiruta H. Advanced Computational Methodology for Full-Core Neutronics Calculations. [Internet] [Doctoral dissertation]. North Carolina State University; 2004. [cited 2019 Feb 16]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/5463.

Council of Science Editors:

Hiruta H. Advanced Computational Methodology for Full-Core Neutronics Calculations. [Doctoral Dissertation]. North Carolina State University; 2004. Available from: http://www.lib.ncsu.edu/resolver/1840.16/5463

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

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 February 16, 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. 16 Feb 2019.

Vancouver:

Talley KD. Beta-Delayed Neutron Data and Models for SCALE. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2019 Feb 16]. 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

23. 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 February 16, 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. 16 Feb 2019.

Vancouver:

Serra AdS. Determinação experimental da reatividade subcrítica utilizando correlação de terceira ordem. [Internet] [Doctoral dissertation]. University of São Paulo; 2012. [cited 2019 Feb 16]. 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

24. 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 (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 February 16, 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. 16 Feb 2019.

Vancouver:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. 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


KTH

25. Kotchoubey, Jurij. POLCA-T Neutron Kinetics Model Benchmarking.

Degree: Reactor Technology, 2015, KTH

  The demand for computational tools that are capable to reliably predict the behavior of a nuclear reactor core in a variety of static and… (more)

Subjects/Keywords: POLCA-T; Neutronics; Neutron Kinetics; Benchmarking; Reactor Kinetics; Space-Time Kinetics; Reactor Physics; POLCA-T; Kinetik; Neutronkinetik; Benchmarking; Reaktorfysik

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APA (6th Edition):

Kotchoubey, J. (2015). POLCA-T Neutron Kinetics Model Benchmarking. (Thesis). KTH. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-176096

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):

Kotchoubey, Jurij. “POLCA-T Neutron Kinetics Model Benchmarking.” 2015. Thesis, KTH. Accessed February 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-176096.

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

MLA Handbook (7th Edition):

Kotchoubey, Jurij. “POLCA-T Neutron Kinetics Model Benchmarking.” 2015. Web. 16 Feb 2019.

Vancouver:

Kotchoubey J. POLCA-T Neutron Kinetics Model Benchmarking. [Internet] [Thesis]. KTH; 2015. [cited 2019 Feb 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-176096.

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

Council of Science Editors:

Kotchoubey J. POLCA-T Neutron Kinetics Model Benchmarking. [Thesis]. KTH; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-176096

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

26. 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 (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 February 16, 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. 16 Feb 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 Feb 16]. 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

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

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 February 16, 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. 16 Feb 2019.

Vancouver:

Tan A. Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code. [Internet] [Masters thesis]. McMaster University; 2015. [cited 2019 Feb 16]. 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

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

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 February 16, 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. 16 Feb 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 Feb 16]. 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


University of Ontario Institute of Technology

29. Colton, Ashlea V. K. Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients.

Degree: 2016, University of Ontario Institute of Technology

 To model the neutronic physics behavior of the core in CANDU pressure tube type heavy water reactors with natural-uranium fuel, two levels of calculations are… (more)

Subjects/Keywords: Reactor physics; Diffusion theory; Heavy water reactors; Natural uranium; Core reflector interface

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APA (6th Edition):

Colton, A. V. K. (2016). Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/755

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):

Colton, Ashlea V K. “Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients.” 2016. Thesis, University of Ontario Institute of Technology. Accessed February 16, 2019. http://hdl.handle.net/10155/755.

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

MLA Handbook (7th Edition):

Colton, Ashlea V K. “Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients.” 2016. Web. 16 Feb 2019.

Vancouver:

Colton AVK. Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/10155/755.

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

Council of Science Editors:

Colton AVK. Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients. [Thesis]. University of Ontario Institute of Technology; 2016. Available from: http://hdl.handle.net/10155/755

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

30. Rossi, Lubianka Ferrari Russo. Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear.

Degree: PhD, Tecnologia Nuclear - Reatores, 2014, University of São Paulo

Este trabalho apresenta um novo método para o cálculo dos coecientes de sensibilidade, através da união do metodo diferencial e da teoria da perturbação generalizada,… (more)

Subjects/Keywords: analise de sensibilidade; coeficientes de sensibilidade; física de reatores; reactor physics; sensibility analysis; sensitivity coecients

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

APA (6th Edition):

Rossi, L. F. R. (2014). Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12022015-154545/ ;

Chicago Manual of Style (16th Edition):

Rossi, Lubianka Ferrari Russo. “Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear.” 2014. Doctoral Dissertation, University of São Paulo. Accessed February 16, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12022015-154545/ ;.

MLA Handbook (7th Edition):

Rossi, Lubianka Ferrari Russo. “Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear.” 2014. Web. 16 Feb 2019.

Vancouver:

Rossi LFR. Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear. [Internet] [Doctoral dissertation]. University of São Paulo; 2014. [cited 2019 Feb 16]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12022015-154545/ ;.

Council of Science Editors:

Rossi LFR. Acoplamento entre os métodos diferencial e da teoria da perturbação para o cálculo dos coeficientes de sensibilidade em problemas de transmutação nuclear. [Doctoral Dissertation]. University of São Paulo; 2014. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12022015-154545/ ;

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