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Level: masters

You searched for subject:(nuclear reactor physics). Showing records 1 – 11 of 11 total matches.

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McMaster University

1. 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 July 21, 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. 21 Jul 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 Jul 21]. 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


McMaster University

2. 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 July 21, 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. 21 Jul 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 Jul 21]. 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

3. 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 July 21, 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. 21 Jul 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 Jul 21]. 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


McMaster University

4. 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 July 21, 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. 21 Jul 2019.

Vancouver:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 Jul 21]. 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

5. 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 July 21, 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. 21 Jul 2019.

Vancouver:

Tan A. Transient Simulations of the SLOWPOKE-2 Reactor Using the G4-STORK Code. [Internet] [Masters thesis]. McMaster University; 2015. [cited 2019 Jul 21]. 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


Missouri University of Science and Technology

6. 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 July 21, 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. 21 Jul 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 Jul 21]. 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

7. 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 July 21, 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. 21 Jul 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Jul 21]. 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

8. 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 July 21, 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. 21 Jul 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 Jul 21]. 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/ ;


The Ohio State University

9. 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 July 21, 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. 21 Jul 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 Jul 21]. 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

10. Bhattacharyya, Sampriti. Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X.

Degree: MS, Aero/Astro Engineering, 2012, The Ohio State University

Nuclear energy has tremendous potential as a reliable source of cheap, clean energy. The key impediments to expanded use of nuclear energy are safety… (more)

Subjects/Keywords: Aerospace Engineering; Energy; Engineering; Nuclear Engineering; Nuclear Physics; Particle Physics; Accelerator Driven Systems; Thorium Reactor; Project X; beam modeling; controls

…Systems (ADS) (2) – a nuclear reactor that uses a linac like Project X for… …Muon physics and nuclear physics, including ADS research. The higher energy section from 3–8… …reliability modeling methodologies as needed by Fermilab for their fundamental physics experiments… …can be applied. The problem has mostly been treated in the physics domain, and yet has… …physics, discusses the aspects of accelerator engineering – different subsystems involved and… 

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APA (6th Edition):

Bhattacharyya, S. (2012). Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1343340152

Chicago Manual of Style (16th Edition):

Bhattacharyya, Sampriti. “Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X.” 2012. Masters Thesis, The Ohio State University. Accessed July 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1343340152.

MLA Handbook (7th Edition):

Bhattacharyya, Sampriti. “Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X.” 2012. Web. 21 Jul 2019.

Vancouver:

Bhattacharyya S. Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Jul 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1343340152.

Council of Science Editors:

Bhattacharyya S. Reliability Analysis and Controls for Accelerator Driven Systems Based On Project X. [Masters Thesis]. The Ohio State University; 2012. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1343340152

11. Grabaskas, David. Analysis of Transient Overpower Scenarios in Sodium Fast Reactors.

Degree: MS, Nuclear Engineering, 2010, The Ohio State University

 The objective of this research was the demonstration of a methodology to handle epistemic and aleatory uncertainties within an unprotected transient overpower (TOP) scenario in… (more)

Subjects/Keywords: Engineering; Nuclear Physics; Sodium Fast Reactor; Unprotected Transient Overpower; Uncertainty Analysis; Aleatory Uncertainty; Epistemic Uncertainty

…liquid metal fast reactor built, and the first nuclear reactor to create electrical power, was… …CHAPTER 1 INTRODUCTION As part of a joint Nuclear Energy Research Initiative (NERI)… …State University, an investigation was launched regarding sodium reactor accident transient… …ways to reduce the costs of the reactor while ensuring that it will meet future safety and… …kinds of accident scenarios than for light water reactors. Light water reactor safety concerns… 

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APA (6th Edition):

Grabaskas, D. (2010). Analysis of Transient Overpower Scenarios in Sodium Fast Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1265726176

Chicago Manual of Style (16th Edition):

Grabaskas, David. “Analysis of Transient Overpower Scenarios in Sodium Fast Reactors.” 2010. Masters Thesis, The Ohio State University. Accessed July 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1265726176.

MLA Handbook (7th Edition):

Grabaskas, David. “Analysis of Transient Overpower Scenarios in Sodium Fast Reactors.” 2010. Web. 21 Jul 2019.

Vancouver:

Grabaskas D. Analysis of Transient Overpower Scenarios in Sodium Fast Reactors. [Internet] [Masters thesis]. The Ohio State University; 2010. [cited 2019 Jul 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1265726176.

Council of Science Editors:

Grabaskas D. Analysis of Transient Overpower Scenarios in Sodium Fast Reactors. [Masters Thesis]. The Ohio State University; 2010. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1265726176

.