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You searched for subject:(Neutronics). Showing records 1 – 30 of 44 total matches.

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McMaster University

1. Hummel, David. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.

Degree: PhD, 2015, McMaster University

The Generation IV International Forum has established several goals for the next generation of nuclear energy systems, which are to be substantial improvements over contemporary… (more)

Subjects/Keywords: SCWR; Neutronics; Thermalhydraulics; Coupling

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APA (6th Edition):

Hummel, D. (2015). Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/18363

Chicago Manual of Style (16th Edition):

Hummel, David. “Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.” 2015. Doctoral Dissertation, McMaster University. Accessed January 21, 2019. http://hdl.handle.net/11375/18363.

MLA Handbook (7th Edition):

Hummel, David. “Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.” 2015. Web. 21 Jan 2019.

Vancouver:

Hummel D. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. [Internet] [Doctoral dissertation]. McMaster University; 2015. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/11375/18363.

Council of Science Editors:

Hummel D. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. [Doctoral Dissertation]. McMaster University; 2015. Available from: http://hdl.handle.net/11375/18363


University of Ontario Institute of Technology

2. Peiman, Wargha. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).

Degree: 2017, University of Ontario Institute of Technology

 A group of countries has initiated an international collaboration to develop a next generation (i.e., Generation IV) of nuclear reactors. Chosen as one of the… (more)

Subjects/Keywords: SCWR; Thermalhydraulics; Neutronics; Generation IV; Nuclear fuel

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APA (6th Edition):

Peiman, W. (2017). Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/827

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):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Thesis, University of Ontario Institute of Technology. Accessed January 21, 2019. http://hdl.handle.net/10155/827.

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

MLA Handbook (7th Edition):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Web. 21 Jan 2019.

Vancouver:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Internet] [Thesis]. University of Ontario Institute of Technology; 2017. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/10155/827.

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

Council of Science Editors:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Thesis]. University of Ontario Institute of Technology; 2017. Available from: http://hdl.handle.net/10155/827

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


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 January 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 Jan 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 Jan 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


Penn State University

4. Rosenkrantz, Adam Matthew. Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor.

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

 The purpose of this study was to create a highly accurate model of the SAFARI-1 materials testing reactor, a facility mainly used for research and… (more)

Subjects/Keywords: Neutronics; Thermal Hydraulics; Modeling; Nuclear; Reactor; Coupling; Engineering

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APA (6th Edition):

Rosenkrantz, A. M. (2012). Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/13747

Chicago Manual of Style (16th Edition):

Rosenkrantz, Adam Matthew. “Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor.” 2012. Masters Thesis, Penn State University. Accessed January 21, 2019. https://etda.libraries.psu.edu/catalog/13747.

MLA Handbook (7th Edition):

Rosenkrantz, Adam Matthew. “Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor.” 2012. Web. 21 Jan 2019.

Vancouver:

Rosenkrantz AM. Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor. [Internet] [Masters thesis]. Penn State University; 2012. [cited 2019 Jan 21]. Available from: https://etda.libraries.psu.edu/catalog/13747.

Council of Science Editors:

Rosenkrantz AM. Coupled 3D Neutronics and Thermal Hydraulics Modeling of the SAFARI-1 Materials Testing Reactor. [Masters Thesis]. Penn State University; 2012. Available from: https://etda.libraries.psu.edu/catalog/13747


Virginia Commonwealth University

5. Britton, Kyle A. Neutronics Studies on the NIST Reactor Using the GA LEU fuel.

Degree: MS, Mechanical and Nuclear Engineering, 2018, Virginia Commonwealth University

  The National Bureau of Standards Reactor (NBSR) located on the National Institute of Standards and Technology (NIST) Gaithersburg campus, is currently underway of fuel… (more)

Subjects/Keywords: Neutronics; NBSR; TRIGA fuel; LEU fuel; Research Reactor; Nuclear; Nuclear Engineering

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APA (6th Edition):

Britton, K. A. (2018). Neutronics Studies on the NIST Reactor Using the GA LEU fuel. (Thesis). Virginia Commonwealth University. Retrieved from https://scholarscompass.vcu.edu/etd/5702

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):

Britton, Kyle A. “Neutronics Studies on the NIST Reactor Using the GA LEU fuel.” 2018. Thesis, Virginia Commonwealth University. Accessed January 21, 2019. https://scholarscompass.vcu.edu/etd/5702.

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

MLA Handbook (7th Edition):

Britton, Kyle A. “Neutronics Studies on the NIST Reactor Using the GA LEU fuel.” 2018. Web. 21 Jan 2019.

Vancouver:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 Jan 21]. Available from: https://scholarscompass.vcu.edu/etd/5702.

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

Council of Science Editors:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Thesis]. Virginia Commonwealth University; 2018. Available from: https://scholarscompass.vcu.edu/etd/5702

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


Georgia Tech

6. Burns, Joseph Raymond. Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor.

Degree: PhD, Mechanical Engineering, 2017, Georgia Tech

 One of the key challenges to the advancement of nuclear power technology nationally and globally is the substantial upfront capital investment required for the construction… (more)

Subjects/Keywords: Neutronics; Additive manufacturing; High flux isotope reactor; Optimization

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APA (6th Edition):

Burns, J. R. (2017). Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59270

Chicago Manual of Style (16th Edition):

Burns, Joseph Raymond. “Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor.” 2017. Doctoral Dissertation, Georgia Tech. Accessed January 21, 2019. http://hdl.handle.net/1853/59270.

MLA Handbook (7th Edition):

Burns, Joseph Raymond. “Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor.” 2017. Web. 21 Jan 2019.

Vancouver:

Burns JR. Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor. [Internet] [Doctoral dissertation]. Georgia Tech; 2017. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/1853/59270.

Council of Science Editors:

Burns JR. Neutronic modeling and design optimization of additively manufactured control elements for the high flux isotope reactor. [Doctoral Dissertation]. Georgia Tech; 2017. Available from: http://hdl.handle.net/1853/59270


Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ)

7. Mylonakis, Antonios. Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback.

Degree: 2017, Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ)

Some of the most important challenges that the Monte-Carlo based analysis of the nuclear reactor core physics faces nowadays are the insertion of efficient thermal-hydraulic… (more)

Subjects/Keywords: Πυρηνικός αντιδραστήρας; Νετρονική ανάλυση; Monte-Carlo; Monte-Carlo; Nuclear reactor; Neutronics

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APA (6th Edition):

Mylonakis, A. (2017). Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback. (Thesis). Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ). Retrieved from http://hdl.handle.net/10442/hedi/41976

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):

Mylonakis, Antonios. “Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback.” 2017. Thesis, Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ). Accessed January 21, 2019. http://hdl.handle.net/10442/hedi/41976.

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

MLA Handbook (7th Edition):

Mylonakis, Antonios. “Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback.” 2017. Web. 21 Jan 2019.

Vancouver:

Mylonakis A. Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback. [Internet] [Thesis]. Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ); 2017. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/10442/hedi/41976.

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

Council of Science Editors:

Mylonakis A. Static and dynamic stochastic neutronic reactor analysis with thermal-hydraulic feedback. [Thesis]. Aristotle University Of Thessaloniki (AUTH); Αριστοτέλειο Πανεπιστήμιο Θεσσαλονίκης (ΑΠΘ); 2017. Available from: http://hdl.handle.net/10442/hedi/41976

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


KTH

8. 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 January 21, 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. 21 Jan 2019.

Vancouver:

Luszczek K. Validation and Benchmarking of Westinghouse BWR lattice physics methods. [Internet] [Thesis]. KTH; 2015. [cited 2019 Jan 21]. 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


North-West University

9. Montwedi, Ontlametse Emmanuel. Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi .

Degree: 2014, North-West University

 The South African government’s integrated resource plan for electricity IRP2010 states that the country plans to have an additional 9.6 GW of nuclear power on… (more)

Subjects/Keywords: Nuclear; Neutronics; MCNP; EPR; Power profile; Flux; Convergence; Rods worth

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APA (6th Edition):

Montwedi, O. E. (2014). Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi . (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/15437

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):

Montwedi, Ontlametse Emmanuel. “Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi .” 2014. Thesis, North-West University. Accessed January 21, 2019. http://hdl.handle.net/10394/15437.

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

MLA Handbook (7th Edition):

Montwedi, Ontlametse Emmanuel. “Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi .” 2014. Web. 21 Jan 2019.

Vancouver:

Montwedi OE. Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi . [Internet] [Thesis]. North-West University; 2014. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/10394/15437.

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

Council of Science Editors:

Montwedi OE. Neutronic simulation of a European Pressurised Reactor / Ontlametse Emmanuel Montwedi . [Thesis]. North-West University; 2014. Available from: http://hdl.handle.net/10394/15437

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

10. Jareteg, Klas. Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver.

Degree: 2012, Chalmers University of Technology

 In LWR cores, multiple fields of physics will need to be tackled. The power level is determined by the neutron density field, and the generated… (more)

Subjects/Keywords: high-fidelity; neutronics; thermal-hydraulics; CFD; multi-physics; coupled deterministic modeling; LWR

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APA (6th Edition):

Jareteg, K. (2012). Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/159104-development-of-an-integrated-deterministic-neutronicthermal-hydraulic-model-using-a-cfd-solver

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):

Jareteg, Klas. “Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver.” 2012. Thesis, Chalmers University of Technology. Accessed January 21, 2019. http://studentarbeten.chalmers.se/publication/159104-development-of-an-integrated-deterministic-neutronicthermal-hydraulic-model-using-a-cfd-solver.

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

MLA Handbook (7th Edition):

Jareteg, Klas. “Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver.” 2012. Web. 21 Jan 2019.

Vancouver:

Jareteg K. Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver. [Internet] [Thesis]. Chalmers University of Technology; 2012. [cited 2019 Jan 21]. Available from: http://studentarbeten.chalmers.se/publication/159104-development-of-an-integrated-deterministic-neutronicthermal-hydraulic-model-using-a-cfd-solver.

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

Council of Science Editors:

Jareteg K. Development of an integrated deterministic neutronic/thermal-hydraulic model using a CFD solver. [Thesis]. Chalmers University of Technology; 2012. Available from: http://studentarbeten.chalmers.se/publication/159104-development-of-an-integrated-deterministic-neutronicthermal-hydraulic-model-using-a-cfd-solver

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


Texas A&M University

11. Kitcher, Evans Damenortey, 1987-. Performance and Safety Analysis of a Generic Small Modular Reactor.

Degree: 2012, Texas A&M University

 The high and ever growing demand for electricity coupled with environmental concerns and a worldwide desire to shed petroleum dependence, all point to a shift… (more)

Subjects/Keywords: Assessment; Proliferation Resistance; Single Channel Analysis; Neutronics Analysis; Water Reactor; Integral Pressurized; Small Modular Reactor

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APA (6th Edition):

Kitcher, Evans Damenortey, 1. (2012). Performance and Safety Analysis of a Generic Small Modular Reactor. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148135

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, 1987-. “Performance and Safety Analysis of a Generic Small Modular Reactor.” 2012. Thesis, Texas A&M University. Accessed January 21, 2019. http://hdl.handle.net/1969.1/148135.

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, 1987-. “Performance and Safety Analysis of a Generic Small Modular Reactor.” 2012. Web. 21 Jan 2019.

Vancouver:

Kitcher, Evans Damenortey 1. Performance and Safety Analysis of a Generic Small Modular Reactor. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/1969.1/148135.

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

Council of Science Editors:

Kitcher, Evans Damenortey 1. Performance and Safety Analysis of a Generic Small Modular Reactor. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148135

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


McMaster University

12. 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 January 21, 2019. http://hdl.handle.net/11375/22064.

MLA Handbook (7th Edition):

Sharpe, Jason. “Innovative Analysis Techniques for Canadian SCWR Neutronics.” 2017. Web. 21 Jan 2019.

Vancouver:

Sharpe J. Innovative Analysis Techniques for Canadian SCWR Neutronics. [Internet] [Doctoral dissertation]. McMaster University; 2017. [cited 2019 Jan 21]. 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


University of Illinois – Urbana-Champaign

13. Rivera, Jose E. Neutronics analysis for cylindrical assembly using Green's functions.

Degree: MS, 5183, 2011, University of Illinois – Urbana-Champaign

 When designing a reactor a preliminary design is done in order to obtain a rough estimate of various reactor properties. These properties include the neutron… (more)

Subjects/Keywords: Neutronics; Cylindrical Assembly; Neutron Diffusion in Cylindrical Coordinates; Green's Function Matrix; Chopped Cosine

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APA (6th Edition):

Rivera, J. E. (2011). Neutronics analysis for cylindrical assembly using Green's functions. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/24034

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):

Rivera, Jose E. “Neutronics analysis for cylindrical assembly using Green's functions.” 2011. Thesis, University of Illinois – Urbana-Champaign. Accessed January 21, 2019. http://hdl.handle.net/2142/24034.

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

MLA Handbook (7th Edition):

Rivera, Jose E. “Neutronics analysis for cylindrical assembly using Green's functions.” 2011. Web. 21 Jan 2019.

Vancouver:

Rivera JE. Neutronics analysis for cylindrical assembly using Green's functions. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2011. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/2142/24034.

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

Council of Science Editors:

Rivera JE. Neutronics analysis for cylindrical assembly using Green's functions. [Thesis]. University of Illinois – Urbana-Champaign; 2011. Available from: http://hdl.handle.net/2142/24034

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

14. Andersson, Rasmus. Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework.

Degree: 2015, Chalmers University of Technology

 The aim of this thesis is to develop and implement a code for solving the coupled multiphysics of PWR fuel assemblies at transient conditions using… (more)

Subjects/Keywords: Multiphysics; neutronics; thermal-hydraulics; CFD; deterministic reactor modeling; conjugate heat transfer; diffusion; discrete ordinates method; OpenFOAM

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APA (6th Edition):

Andersson, R. (2015). Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/218901-development-of-a-transient-multiphysics-solver-for-nuclear-fuel-assemblies-within-a-cfd-framework

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):

Andersson, Rasmus. “Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework.” 2015. Thesis, Chalmers University of Technology. Accessed January 21, 2019. http://studentarbeten.chalmers.se/publication/218901-development-of-a-transient-multiphysics-solver-for-nuclear-fuel-assemblies-within-a-cfd-framework.

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

MLA Handbook (7th Edition):

Andersson, Rasmus. “Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework.” 2015. Web. 21 Jan 2019.

Vancouver:

Andersson R. Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework. [Internet] [Thesis]. Chalmers University of Technology; 2015. [cited 2019 Jan 21]. Available from: http://studentarbeten.chalmers.se/publication/218901-development-of-a-transient-multiphysics-solver-for-nuclear-fuel-assemblies-within-a-cfd-framework.

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

Council of Science Editors:

Andersson R. Development of a transient multiphysics solver for nuclear fuel assemblies within a CFD framework. [Thesis]. Chalmers University of Technology; 2015. Available from: http://studentarbeten.chalmers.se/publication/218901-development-of-a-transient-multiphysics-solver-for-nuclear-fuel-assemblies-within-a-cfd-framework

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

15. Targa, Alexandre. Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel.

Degree: Docteur es, Mécanique des matériaux, 2017, Paris Saclay

L’analyse de sûreté des réacteurs nucléaires nécessite la modélisation fine des phénomènes y survenant et plus spécifiquement ceux permettant d’assurer l’intégrité des barrières de confinement.… (more)

Subjects/Keywords: Neutronique; Physique du Combustible Nucléaire; Thermohydraulique; Modélisation Multiphysique; Analyse Numérique; Neutronics; Nuclear Fuel Physics; Thermohydraulics; Multi-Physics Modeling; Numerical Analysis

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APA (6th Edition):

Targa, A. (2017). Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel. (Doctoral Dissertation). Paris Saclay. Retrieved from http://www.theses.fr/2017SACLX032

Chicago Manual of Style (16th Edition):

Targa, Alexandre. “Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel.” 2017. Doctoral Dissertation, Paris Saclay. Accessed January 21, 2019. http://www.theses.fr/2017SACLX032.

MLA Handbook (7th Edition):

Targa, Alexandre. “Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel.” 2017. Web. 21 Jan 2019.

Vancouver:

Targa A. Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel. [Internet] [Doctoral dissertation]. Paris Saclay; 2017. [cited 2019 Jan 21]. Available from: http://www.theses.fr/2017SACLX032.

Council of Science Editors:

Targa A. Development of multi-physics and multi-scale Best Effort Modelling of pressurized water reactor under accidental situations : Développement de modélisations multi-physiques Best Effort pour une analyse fine des réacteurs à eau pressurisée en conditions de fonctionnement accidentel. [Doctoral Dissertation]. Paris Saclay; 2017. Available from: http://www.theses.fr/2017SACLX032


EPFL

16. Rätz, Dominik. Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs.

Degree: 2012, EPFL

 The Supercritical-Water-Cooled Reactor (SCWR) is the Generation IV reactor concept most closely related to current light water reactors (LWRs). The SCWR builds on the vast… (more)

Subjects/Keywords: SCWR; HPLWR; code validation; neutronics; lattice physics; moderation heterogeneity; CASMO; MCNPX; PROTEUS; reaction rates; reactivity worths

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APA (6th Edition):

Rätz, D. (2012). Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/170290

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):

Rätz, Dominik. “Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs.” 2012. Thesis, EPFL. Accessed January 21, 2019. http://infoscience.epfl.ch/record/170290.

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

MLA Handbook (7th Edition):

Rätz, Dominik. “Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs.” 2012. Web. 21 Jan 2019.

Vancouver:

Rätz D. Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs. [Internet] [Thesis]. EPFL; 2012. [cited 2019 Jan 21]. Available from: http://infoscience.epfl.ch/record/170290.

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

Council of Science Editors:

Rätz D. Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs. [Thesis]. EPFL; 2012. Available from: http://infoscience.epfl.ch/record/170290

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

17. Kooreman, Gabriel. Consistent hybrid diffusion-transport spatial homogenization method.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 Recent work by Yasseri and Rahnema has introduced a consistent spatial homogenization (CSH) method completely in transport theory. The CSH method can very accurately reproduce… (more)

Subjects/Keywords: Reactor physics; Neutronics; Neutron transport; Diffusion; Homogenization

Page 1 Page 2 Page 3 Page 4 Page 5 Page 6 Page 7

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APA (6th Edition):

Kooreman, G. (2013). Consistent hybrid diffusion-transport spatial homogenization method. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/52950

Chicago Manual of Style (16th Edition):

Kooreman, Gabriel. “Consistent hybrid diffusion-transport spatial homogenization method.” 2013. Masters Thesis, Georgia Tech. Accessed January 21, 2019. http://hdl.handle.net/1853/52950.

MLA Handbook (7th Edition):

Kooreman, Gabriel. “Consistent hybrid diffusion-transport spatial homogenization method.” 2013. Web. 21 Jan 2019.

Vancouver:

Kooreman G. Consistent hybrid diffusion-transport spatial homogenization method. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/1853/52950.

Council of Science Editors:

Kooreman G. Consistent hybrid diffusion-transport spatial homogenization method. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/52950


Université de Grenoble

18. Jacquet, Philippe. Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis.

Degree: Docteur es, Mécanique, génie mécanique, 2011, Université de Grenoble

Les critères de sureté qui régissent le développement de coeurs de réacteurs dequatrième génération implique l’usage d’outils de calcul neutronique performants. Unepremière partie de la… (more)

Subjects/Keywords: Neutronique; Calcul cellule; Réacteur rapide; Condensation Energétique; Homogénéisation spatiale; Neutronics; Cell code; Fast reactor; Energy group collapsing; Energy group collapsing; 530

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APA (6th Edition):

Jacquet, P. (2011). Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis. (Doctoral Dissertation). Université de Grenoble. Retrieved from http://www.theses.fr/2011GRENI064

Chicago Manual of Style (16th Edition):

Jacquet, Philippe. “Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis.” 2011. Doctoral Dissertation, Université de Grenoble. Accessed January 21, 2019. http://www.theses.fr/2011GRENI064.

MLA Handbook (7th Edition):

Jacquet, Philippe. “Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis.” 2011. Web. 21 Jan 2019.

Vancouver:

Jacquet P. Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis. [Internet] [Doctoral dissertation]. Université de Grenoble; 2011. [cited 2019 Jan 21]. Available from: http://www.theses.fr/2011GRENI064.

Council of Science Editors:

Jacquet P. Nouvelles méthodes de modélisation neutronique des réacteurs rapides de quatrième Génération : New modelling method for fast reactor neutronic behaviours analysis. [Doctoral Dissertation]. Université de Grenoble; 2011. Available from: http://www.theses.fr/2011GRENI064

19. Ros, Paul. Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications.

Degree: Docteur es, Mécanique des fluides, Procédés, Energétique, 2017, Grenoble Alpes

Les travaux réalisés au cours de cette thèse portent sur la conception neutronique de configurations expérimentale destinées à améliorer la connaissance de paramètres neutroniques, en… (more)

Subjects/Keywords: Coeur couplé; Réacteur expérimental; Optimisation neutronique; Adaptation spectrale; Coupled core; Experimental reactor; Neutronics optimisation; Spectral adaptation; 620

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APA (6th Edition):

Ros, P. (2017). Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications. (Doctoral Dissertation). Grenoble Alpes. Retrieved from http://www.theses.fr/2017GREAI045

Chicago Manual of Style (16th Edition):

Ros, Paul. “Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications.” 2017. Doctoral Dissertation, Grenoble Alpes. Accessed January 21, 2019. http://www.theses.fr/2017GREAI045.

MLA Handbook (7th Edition):

Ros, Paul. “Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications.” 2017. Web. 21 Jan 2019.

Vancouver:

Ros P. Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications. [Internet] [Doctoral dissertation]. Grenoble Alpes; 2017. [cited 2019 Jan 21]. Available from: http://www.theses.fr/2017GREAI045.

Council of Science Editors:

Ros P. Conception neutronique de configurations expérimentales à forte adaptation spectrale en réacteur de puissance nulle pour des applications multi-filières Gen-II,III & IV : Neutronics design of zero power reactor experimental configurations with high spectral adaptation for Gen-II, III & IV reactors applications. [Doctoral Dissertation]. Grenoble Alpes; 2017. Available from: http://www.theses.fr/2017GREAI045


KTH

20. 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 January 21, 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. 21 Jan 2019.

Vancouver:

Kotchoubey J. POLCA-T Neutron Kinetics Model Benchmarking. [Internet] [Thesis]. KTH; 2015. [cited 2019 Jan 21]. 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

21. Wu, Hsingtzu. Tightly coupled neutronics and thermal-hydraulics using open-source software.

Degree: PhD, 0139, 2014, University of Illinois – Urbana-Champaign

 Coupling the neutronic and thermal-hydraulic analyses of a nuclear reactor core is important because it helps identify the most relevant safety issues. Currently all coupled… (more)

Subjects/Keywords: coupling neutronics; tight coupling; thermal-hydraulics

…1.2 An algorithm for loosely coupled neutronics and thermal-hydraulics. . . . . 1.3 A simple… …analyses, one needs the knowledge of both neutronics and thermal-hydraulics: a neutronic… …water Cooled Reactor, the coupling of neutronics and thermal-hydraulics is a necessity to… …thermal-hydraulic feedback mechanisms [5]. 1.1 Coupling Neutronics and Thermal… …Hydraulics for a Nuclear Reactor Core The significance of coupling neutronics and thermal… 

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APA (6th Edition):

Wu, H. (2014). Tightly coupled neutronics and thermal-hydraulics using open-source software. (Doctoral Dissertation). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/46658

Chicago Manual of Style (16th Edition):

Wu, Hsingtzu. “Tightly coupled neutronics and thermal-hydraulics using open-source software.” 2014. Doctoral Dissertation, University of Illinois – Urbana-Champaign. Accessed January 21, 2019. http://hdl.handle.net/2142/46658.

MLA Handbook (7th Edition):

Wu, Hsingtzu. “Tightly coupled neutronics and thermal-hydraulics using open-source software.” 2014. Web. 21 Jan 2019.

Vancouver:

Wu H. Tightly coupled neutronics and thermal-hydraulics using open-source software. [Internet] [Doctoral dissertation]. University of Illinois – Urbana-Champaign; 2014. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/2142/46658.

Council of Science Editors:

Wu H. Tightly coupled neutronics and thermal-hydraulics using open-source software. [Doctoral Dissertation]. University of Illinois – Urbana-Champaign; 2014. Available from: http://hdl.handle.net/2142/46658

22. Wu, Xu. Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback.

Degree: MS, 5183, 2013, University of Illinois – Urbana-Champaign

 The present thesis describes the coupling of a three-dimensional continuous-energy Monte Carlo reactor physics code, Serpent, with thermal-hydraulics safety analysis code RELAP5-3D. Thermal-hydraulics and reactor… (more)

Subjects/Keywords: Monte Carlo; Thermal-hydraulics; Neutronics; Code coupling

Neutronics processes like neutron transport, cross-section dependence on the energy and temperature… …requirements for a coupling of discrete physics. This is fulfilled by coupling neutronics and thermal… …simulation. Researchers have successfully coupled neutronics and thermal-hydraulics codes to… …CFD) code CFX and neutronics code MCNP, in the simulation of Generation IV SCWR (… …challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis. He… 

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APA (6th Edition):

Wu, X. (2013). Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/45550

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):

Wu, Xu. “Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback.” 2013. Thesis, University of Illinois – Urbana-Champaign. Accessed January 21, 2019. http://hdl.handle.net/2142/45550.

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

MLA Handbook (7th Edition):

Wu, Xu. “Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback.” 2013. Web. 21 Jan 2019.

Vancouver:

Wu X. Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2013. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/2142/45550.

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

Council of Science Editors:

Wu X. Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback. [Thesis]. University of Illinois – Urbana-Champaign; 2013. Available from: http://hdl.handle.net/2142/45550

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


University of Florida

23. Hughes, Christopher R. Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application.

Degree: PhD, Mechanical Engineering - Mechanical and Aerospace Engineering, 2016, University of Florida

 The large and continuous density variations with temperature that occur as a supercritical fluid is heated increase the complexity of analysis of the coupled physics… (more)

Subjects/Keywords: Boundary conditions; Geometry; Heat transfer; Neutrons; Reynolds stress; Spectral methods; Tensors; Turbulence models; Velocity; Water temperature; cfd  – dns  – neutronics

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APA (6th Edition):

Hughes, C. R. (2016). Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application. (Doctoral Dissertation). University of Florida. Retrieved from http://ufdc.ufl.edu/UFE0049857

Chicago Manual of Style (16th Edition):

Hughes, Christopher R. “Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application.” 2016. Doctoral Dissertation, University of Florida. Accessed January 21, 2019. http://ufdc.ufl.edu/UFE0049857.

MLA Handbook (7th Edition):

Hughes, Christopher R. “Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application.” 2016. Web. 21 Jan 2019.

Vancouver:

Hughes CR. Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application. [Internet] [Doctoral dissertation]. University of Florida; 2016. [cited 2019 Jan 21]. Available from: http://ufdc.ufl.edu/UFE0049857.

Council of Science Editors:

Hughes CR. Multiphysics Analysis of Supercritical Fluids for Nuclear Reactor Application. [Doctoral Dissertation]. University of Florida; 2016. Available from: http://ufdc.ufl.edu/UFE0049857

24. Shapiro, Rachel Ann. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.

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

 Fully ceramic microencapsulated (FCM) fuel is an accident tolerant design that takes advantage of TRISO technology, embedding the particles in a ceramic matrix (SiC) to… (more)

Subjects/Keywords: PWR; TRISO; accident-tolerant fuel; fully ceramic microencapsulated fuel; neutronics

…necessary. This study investigated the core design, neutronics and thermal-hydraulics of a… …unified energy-grid structure to calculate one group cross sections. 2.2 2.2.1 Neutronics… 

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APA (6th Edition):

Shapiro, R. A. (2014). Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/22708

Chicago Manual of Style (16th Edition):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Masters Thesis, Penn State University. Accessed January 21, 2019. https://etda.libraries.psu.edu/catalog/22708.

MLA Handbook (7th Edition):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Web. 21 Jan 2019.

Vancouver:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Internet] [Masters thesis]. Penn State University; 2014. [cited 2019 Jan 21]. Available from: https://etda.libraries.psu.edu/catalog/22708.

Council of Science Editors:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Masters Thesis]. Penn State University; 2014. Available from: https://etda.libraries.psu.edu/catalog/22708


Université de Grenoble

25. Fabbris, Olivier. Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept.

Degree: Docteur es, Mécanique des fluides, énergétique, procédés, 2014, Université de Grenoble

La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo-hydraulique, thermomécanique du combustible, physique du cycle, etc.). Le problème est aussi de type… (more)

Subjects/Keywords: Optimisation; Multicritère; Multi-physique; RNR-Na; CFV; Coeur de réacteur; Préconception; Neutronique; Thermo-hydraulique; ASTRID; Optimization; Multi-objective; Multi-disciplinary; SFR; CFV; Reactor core; Predesign; Neutronics; Thermal-hydraulics; ASTRID; 620

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APA (6th Edition):

Fabbris, O. (2014). Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept. (Doctoral Dissertation). Université de Grenoble. Retrieved from http://www.theses.fr/2014GRENI055

Chicago Manual of Style (16th Edition):

Fabbris, Olivier. “Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept.” 2014. Doctoral Dissertation, Université de Grenoble. Accessed January 21, 2019. http://www.theses.fr/2014GRENI055.

MLA Handbook (7th Edition):

Fabbris, Olivier. “Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept.” 2014. Web. 21 Jan 2019.

Vancouver:

Fabbris O. Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept. [Internet] [Doctoral dissertation]. Université de Grenoble; 2014. [cited 2019 Jan 21]. Available from: http://www.theses.fr/2014GRENI055.

Council of Science Editors:

Fabbris O. Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV : Multi-objective and multi-physics optimization methodology for SFR core : application to CFV concept. [Doctoral Dissertation]. Université de Grenoble; 2014. Available from: http://www.theses.fr/2014GRENI055

26. Bennett, Alexander Sedgwick. Development and Testing of a Coupled MCNP6/CTF Code.

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

 Current core design methodologies rely on the use of determinstic codes that can run core calculations fast and accuratly. When these deterministic codes are applied… (more)

Subjects/Keywords: Monte Carlo Neutronics; Thermal Hydraulic Subchannel; Coupling; MCNP6; CTF

…these high fidelity codes will be a neutronics code. To achieve a high fidelity solution, the… …neutronics code can be a deterministic code that solves the transport equation for example using… …the method of characteristics, or the neutronics code can be a Monte Carlo code. The… …neutronics code will require information on the temperature distribution, the density distribution… …other coupled Monte Carlo Neutronics/Thermal-hydraulic sub-channel codes, and a description of… 

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

APA (6th Edition):

Bennett, A. S. (2015). Development and Testing of a Coupled MCNP6/CTF Code. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/27383

Chicago Manual of Style (16th Edition):

Bennett, Alexander Sedgwick. “Development and Testing of a Coupled MCNP6/CTF Code.” 2015. Masters Thesis, Penn State University. Accessed January 21, 2019. https://etda.libraries.psu.edu/catalog/27383.

MLA Handbook (7th Edition):

Bennett, Alexander Sedgwick. “Development and Testing of a Coupled MCNP6/CTF Code.” 2015. Web. 21 Jan 2019.

Vancouver:

Bennett AS. Development and Testing of a Coupled MCNP6/CTF Code. [Internet] [Masters thesis]. Penn State University; 2015. [cited 2019 Jan 21]. Available from: https://etda.libraries.psu.edu/catalog/27383.

Council of Science Editors:

Bennett AS. Development and Testing of a Coupled MCNP6/CTF Code. [Masters Thesis]. Penn State University; 2015. Available from: https://etda.libraries.psu.edu/catalog/27383


North-West University

27. Pretorius, Louisa. Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius .

Degree: 2010, North-West University

 The purpose of this study is to evaluate the effects and importance of different cross–section representations and energy group structures for steady state and transient… (more)

Subjects/Keywords: Time Dependent Neutronics and TEmperatures (TINTE); Multi-group TINTE; Energy group structure; Steady state; Transient; Multi-groep TINTE; Energie-groep indeling; Tyd onafhanklik

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APA (6th Edition):

Pretorius, L. (2010). Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius . (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/4947

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):

Pretorius, Louisa. “Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius .” 2010. Thesis, North-West University. Accessed January 21, 2019. http://hdl.handle.net/10394/4947.

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

MLA Handbook (7th Edition):

Pretorius, Louisa. “Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius .” 2010. Web. 21 Jan 2019.

Vancouver:

Pretorius L. Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius . [Internet] [Thesis]. North-West University; 2010. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/10394/4947.

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

Council of Science Editors:

Pretorius L. Comparative study between a two–group and a multi–group energy dynamics code / Louisa Pretorius . [Thesis]. North-West University; 2010. Available from: http://hdl.handle.net/10394/4947

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

28. Xenofontos, Thalia. Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides.

Degree: Docteur es, Énergie nucléaire, 2018, Paris Saclay; Université Aristote (Thessalonique, Grèce)

 La nécessité de simulations précises d’un réacteur nucléaire et spécialement dans des cas de cœurs et de configurations de combustible complexes, a imposé un usage… (more)

Subjects/Keywords: Technologie nucléaire; Neutronique stochastique; Consommation du combustibles innovants; Réacteur Conduit par Accélérateur; Nuclear technology; Stochastic neutronics; Fuel burnup; Accelerator driven systems; 539.707 24

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APA (6th Edition):

Xenofontos, T. (2018). Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides. (Doctoral Dissertation). Paris Saclay; Université Aristote (Thessalonique, Grèce). Retrieved from http://www.theses.fr/2018SACLX013

Chicago Manual of Style (16th Edition):

Xenofontos, Thalia. “Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides.” 2018. Doctoral Dissertation, Paris Saclay; Université Aristote (Thessalonique, Grèce). Accessed January 21, 2019. http://www.theses.fr/2018SACLX013.

MLA Handbook (7th Edition):

Xenofontos, Thalia. “Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides.” 2018. Web. 21 Jan 2019.

Vancouver:

Xenofontos T. Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides. [Internet] [Doctoral dissertation]. Paris Saclay; Université Aristote (Thessalonique, Grèce); 2018. [cited 2019 Jan 21]. Available from: http://www.theses.fr/2018SACLX013.

Council of Science Editors:

Xenofontos T. Development of a dynamic stochastic neutronic code for the analysis of conventional and hybrid nuclear reactors : Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides. [Doctoral Dissertation]. Paris Saclay; Université Aristote (Thessalonique, Grèce); 2018. Available from: http://www.theses.fr/2018SACLX013


Kyoto University / 京都大学

29. Kwon, Saerom. Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究.

Degree: 博士(エネルギー科学), 2014, Kyoto University / 京都大学

新制・課程博士

甲第18388号

エネ博第300号

Subjects/Keywords: Fusion Blanket; Tritium Production; Start-up Scenario; Neutronics; Monte Carlo Method; System Dynamics; Integral Experiment

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APA (6th Edition):

Kwon, S. (2014). Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究. (Thesis). Kyoto University / 京都大学. Retrieved from http://hdl.handle.net/2433/188826 ; http://dx.doi.org/10.14989/doctor.k18388

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):

Kwon, Saerom. “Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究.” 2014. Thesis, Kyoto University / 京都大学. Accessed January 21, 2019. http://hdl.handle.net/2433/188826 ; http://dx.doi.org/10.14989/doctor.k18388.

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

MLA Handbook (7th Edition):

Kwon, Saerom. “Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究.” 2014. Web. 21 Jan 2019.

Vancouver:

Kwon S. Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究. [Internet] [Thesis]. Kyoto University / 京都大学; 2014. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/2433/188826 ; http://dx.doi.org/10.14989/doctor.k18388.

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

Council of Science Editors:

Kwon S. Study on tritium production property by D-T and D-D neutrons of LiPb blanket for fusion reactor : 核融合LiPbブランメットのD-T中性子とD-D中性子によるトリチウム生成に関する研究. [Thesis]. Kyoto University / 京都大学; 2014. Available from: http://hdl.handle.net/2433/188826 ; http://dx.doi.org/10.14989/doctor.k18388

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

30. Hon, Ryan Paul. Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with both UO₂and MOX fuel assemblies. The specification includes heterogeneity at… (more)

Subjects/Keywords: Whole-core transport; Neutronics; PWR benchmarks; Nuclear reactors; Neutron transport theory

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

APA (6th Edition):

Hon, R. P. (2013). Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/47611

Chicago Manual of Style (16th Edition):

Hon, Ryan Paul. “Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes.” 2013. Masters Thesis, Georgia Tech. Accessed January 21, 2019. http://hdl.handle.net/1853/47611.

MLA Handbook (7th Edition):

Hon, Ryan Paul. “Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes.” 2013. Web. 21 Jan 2019.

Vancouver:

Hon RP. Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Jan 21]. Available from: http://hdl.handle.net/1853/47611.

Council of Science Editors:

Hon RP. Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/47611

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