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

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Brunel University

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

Degree: PhD, 1966, Brunel University

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Caulton, Graham K. “The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans.” 1966. Doctoral Dissertation, Brunel University. Accessed July 15, 2019. http://bura.brunel.ac.uk/handle/2438/414 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665.

MLA Handbook (7th Edition):

Caulton, Graham K. “The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans.” 1966. Web. 15 Jul 2019.

Vancouver:

Caulton GK. The design, development and general application of an infra red ratio pyrometer, intended primarily for surface temperature measurement of magnox fuel cans. [Internet] [Doctoral dissertation]. Brunel University; 1966. [cited 2019 Jul 15]. Available from: http://bura.brunel.ac.uk/handle/2438/414 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.557665.

Council of Science Editors:

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


Delft University of Technology

2. Uyttenhove, W. Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems.

Degree: 2016, Delft University of Technology

 This thesis provides a methodology and set-up of a reactivity monitoring tool for Accelerator-Driven Systems (ADS). The reactivity monitoring tool should guarantee the operation of… (more)

Subjects/Keywords: nuclear; accelerator-driven systems; reactivity; reactor physics; experiments; modal analysis; VENUS; MYRRHA

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APA (6th Edition):

Uyttenhove, W. (2016). Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems. (Doctoral Dissertation). Delft University of Technology. Retrieved from http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38

Chicago Manual of Style (16th Edition):

Uyttenhove, W. “Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems.” 2016. Doctoral Dissertation, Delft University of Technology. Accessed July 15, 2019. http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38.

MLA Handbook (7th Edition):

Uyttenhove, W. “Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems.” 2016. Web. 15 Jul 2019.

Vancouver:

Uyttenhove W. Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems. [Internet] [Doctoral dissertation]. Delft University of Technology; 2016. [cited 2019 Jul 15]. Available from: http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38.

Council of Science Editors:

Uyttenhove W. Reactivity Monitoring of Accelerator-Driven Nuclear Reactor Systems. [Doctoral Dissertation]. Delft University of Technology; 2016. Available from: http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; urn:NBN:nl:ui:24-uuid:233dee24-be56-4534-aa3d-e325fe433a38 ; http://resolver.tudelft.nl/uuid:233dee24-be56-4534-aa3d-e325fe433a38


ETH Zürich

3. Hänggi, Philipp. Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics.

Degree: 2001, ETH Zürich

Subjects/Keywords: KERNSTABILITÄT (KERNPHYSIK); KERNREAKTORSICHERHEIT (KERNTECHNIK); COMPUTERANWENDUNGEN/KERNTECHNIK; NUCLEAR STABILITY (NUCLEAR PHYSICS); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); COMPUTER APPLICATIONS IN NUCLEAR TECHNOLOGY; info:eu-repo/classification/ddc/333.7; Natural resources, energy and environment

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APA (6th Edition):

Hänggi, P. (2001). Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/145690

Chicago Manual of Style (16th Edition):

Hänggi, Philipp. “Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics.” 2001. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/145690.

MLA Handbook (7th Edition):

Hänggi, Philipp. “Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics.” 2001. Web. 15 Jul 2019.

Vancouver:

Hänggi P. Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics. [Internet] [Doctoral dissertation]. ETH Zürich; 2001. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/145690.

Council of Science Editors:

Hänggi P. Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics. [Doctoral Dissertation]. ETH Zürich; 2001. Available from: http://hdl.handle.net/20.500.11850/145690


ETH Zürich

4. D’Aleo, Francesco. Surface sensors for temperature and liquid thickness measurement.

Degree: 2014, ETH Zürich

Subjects/Keywords: TEMPERATURMESSUNG + THERMOMETER (WÄRMELEHRE); HEAT TRANSFER; REPEATED DYNAMIC STRESS TESTS (MATERIALS TESTING); KERNREAKTORSICHERHEIT (KERNTECHNIK); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); WECHSELFESTIGKEITSPRÜFUNG (MATERIALPRÜFUNG); TEMPERATURE + THERMOMETRY (THERMOPHYSICS); WÄRMEÜBERGANG; MEASURING DEVICES, SENSORS, DETECTORS (PHYSICS); MESSTECHNISCHE SONDEN, SENSOREN, DETEKTOREN (PHYSIK); info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/530; Natural resources, energy and environment; Physics

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APA (6th Edition):

D’Aleo, F. (2014). Surface sensors for temperature and liquid thickness measurement. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/99067

Chicago Manual of Style (16th Edition):

D’Aleo, Francesco. “Surface sensors for temperature and liquid thickness measurement.” 2014. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/99067.

MLA Handbook (7th Edition):

D’Aleo, Francesco. “Surface sensors for temperature and liquid thickness measurement.” 2014. Web. 15 Jul 2019.

Vancouver:

D’Aleo F. Surface sensors for temperature and liquid thickness measurement. [Internet] [Doctoral dissertation]. ETH Zürich; 2014. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/99067.

Council of Science Editors:

D’Aleo F. Surface sensors for temperature and liquid thickness measurement. [Doctoral Dissertation]. ETH Zürich; 2014. Available from: http://hdl.handle.net/20.500.11850/99067


ETH Zürich

5. Kickhofel, John. Mixing Phenomena Relevant to Thermal Fatigue in T-junctions.

Degree: 2015, ETH Zürich

Subjects/Keywords: FATIGUE RESISTANCE, LOAD-CYCLE STRENGTH (ELASTOMECHANICS); KERNREAKTORSICHERHEIT (KERNTECHNIK); PIPE CONNECTIONS; THERMAL HYDRAULICS (NUCLEAR ENGINEERING); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); THERMOHYDRAULIK (KERNTECHNIK); ROHRVERBINDUNGEN; ERMÜDUNG, WECHSELFESTIGKEIT (ELASTOMECHANIK); info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/530; Natural resources, energy and environment; Physics

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APA (6th Edition):

Kickhofel, J. (2015). Mixing Phenomena Relevant to Thermal Fatigue in T-junctions. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/113631

Chicago Manual of Style (16th Edition):

Kickhofel, John. “Mixing Phenomena Relevant to Thermal Fatigue in T-junctions.” 2015. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/113631.

MLA Handbook (7th Edition):

Kickhofel, John. “Mixing Phenomena Relevant to Thermal Fatigue in T-junctions.” 2015. Web. 15 Jul 2019.

Vancouver:

Kickhofel J. Mixing Phenomena Relevant to Thermal Fatigue in T-junctions. [Internet] [Doctoral dissertation]. ETH Zürich; 2015. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/113631.

Council of Science Editors:

Kickhofel J. Mixing Phenomena Relevant to Thermal Fatigue in T-junctions. [Doctoral Dissertation]. ETH Zürich; 2015. Available from: http://hdl.handle.net/20.500.11850/113631


ETH Zürich

6. Murer, David Emmanuel. He-4 fast neutron detectors in nuclear security applications.

Degree: 2014, ETH Zürich

Subjects/Keywords: SZINTILLATIONSZÄHLER (KERNPHYSIKALISCHE METHODEN); EICHUNG UND PRÜFUNG VON MESSGERÄTEN (PHYSIK); REAKTORKINETIK/SCHNELLE NEUTRONEN (KERNTECHNIK); HELIUM-4-ISOTOP; KERNREAKTORSICHERHEIT (KERNTECHNIK); SCINTILLATION COUNTERS (NUCLEAR METHODS); CALIBRATION AND TESTING OF INSTRUMENTS (PHYSICS); REACTOR KINETICS/FAST NEUTRONS (NUCLEAR ENGINEERING); HELIUM-4 ISOTOPE; NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/530; Natural resources, energy and environment; Physics

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APA (6th Edition):

Murer, D. E. (2014). He-4 fast neutron detectors in nuclear security applications. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/154494

Chicago Manual of Style (16th Edition):

Murer, David Emmanuel. “He-4 fast neutron detectors in nuclear security applications.” 2014. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/154494.

MLA Handbook (7th Edition):

Murer, David Emmanuel. “He-4 fast neutron detectors in nuclear security applications.” 2014. Web. 15 Jul 2019.

Vancouver:

Murer DE. He-4 fast neutron detectors in nuclear security applications. [Internet] [Doctoral dissertation]. ETH Zürich; 2014. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/154494.

Council of Science Editors:

Murer DE. He-4 fast neutron detectors in nuclear security applications. [Doctoral Dissertation]. ETH Zürich; 2014. Available from: http://hdl.handle.net/20.500.11850/154494


ETH Zürich

7. Ylönen, Arto T. High-resolution flow structure measurements in a rod bundle.

Degree: 2013, ETH Zürich

Subjects/Keywords: KÜHLMITTELDRUCKMESSUNG + KÜHLMITTELSTRÖMUNGSMESSUNG (KERNTECHNIK); TURBULENTE STRÖMUNG (FLUIDDYNAMIK); COOLANT PRESSURE MEASUREMENT + COOLANT CURRENT MEASUREMENT (NUCLEAR ENGINEERING); MIXED-PHASE FLOW, FOAMS AND EMULSIONS (FLUID DYNAMICS); TURBULENT FLOW (FLUID DYNAMICS); REAKTORKÜHLUNG (KERNTECHNIK); GAS-FLÜSSIGKEITSGEMISCHE/EMULSIONEN (FLUIDDYNAMIK); REACTOR COOLING (NUCLEAR ENGINEERING); info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/530; Natural resources, energy and environment; Physics

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APA (6th Edition):

Ylönen, A. T. (2013). High-resolution flow structure measurements in a rod bundle. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/65480

Chicago Manual of Style (16th Edition):

Ylönen, Arto T. “High-resolution flow structure measurements in a rod bundle.” 2013. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/65480.

MLA Handbook (7th Edition):

Ylönen, Arto T. “High-resolution flow structure measurements in a rod bundle.” 2013. Web. 15 Jul 2019.

Vancouver:

Ylönen AT. High-resolution flow structure measurements in a rod bundle. [Internet] [Doctoral dissertation]. ETH Zürich; 2013. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/65480.

Council of Science Editors:

Ylönen AT. High-resolution flow structure measurements in a rod bundle. [Doctoral Dissertation]. ETH Zürich; 2013. Available from: http://hdl.handle.net/20.500.11850/65480


ETH Zürich

8. Betschart, Torsten Thomas. Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles.

Degree: 2015, ETH Zürich

Subjects/Keywords: MEHRPHASENSTRÖMUNG (FLUIDDYNAMIK); GAS-FLÜSSIGKEITSGEMISCHE, MISCHPHASENSTRÖMUNG (FLUIDDYNAMIK); STRÖMUNG IN RÖHREN (FLUIDDYNAMIK); GASBLASENBEWEGUNG + TROPFENBEWEGUNG (FLUIDDYNAMIK); KERNREAKTORSICHERHEIT (KERNTECHNIK); MULTIPHASE FLOW (FLUID DYNAMICS); FLOW OF MIXTURES OF GASES AND LIQUIDS (FLUID DYNAMICS); FLOW IN TUBES, PIPES, CLOSED CONDUITS (FLUID DYNAMICS); GAS-BUBBLE MOTION + DROP DYNAMICS (FLUID DYNAMICS); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); info:eu-repo/classification/ddc/530; info:eu-repo/classification/ddc/333.7; Physics; Natural resources, energy and environment

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APA (6th Edition):

Betschart, T. T. (2015). Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/155689

Chicago Manual of Style (16th Edition):

Betschart, Torsten Thomas. “Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles.” 2015. Doctoral Dissertation, ETH Zürich. Accessed July 15, 2019. http://hdl.handle.net/20.500.11850/155689.

MLA Handbook (7th Edition):

Betschart, Torsten Thomas. “Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles.” 2015. Web. 15 Jul 2019.

Vancouver:

Betschart TT. Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles. [Internet] [Doctoral dissertation]. ETH Zürich; 2015. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/20.500.11850/155689.

Council of Science Editors:

Betschart TT. Two-Phase Flow Investigations in Large Diameter Channels and Tube Bundles. [Doctoral Dissertation]. ETH Zürich; 2015. Available from: http://hdl.handle.net/20.500.11850/155689

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

Degree: PhD, Mechanical Engineering, 2017, Georgia Tech

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Huang, Lloyd Michael. “Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning.” 2017. Doctoral Dissertation, Georgia Tech. Accessed July 15, 2019. http://hdl.handle.net/1853/58712.

MLA Handbook (7th Edition):

Huang, Lloyd Michael. “Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning.” 2017. Web. 15 Jul 2019.

Vancouver:

Huang LM. Neutronic analysis and optimization of the advanced high temperature reactor fuel design using machine learning. [Internet] [Doctoral dissertation]. Georgia Tech; 2017. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/1853/58712.

Council of Science Editors:

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

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

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Laureau, Axel. “Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters.” 2015. Doctoral Dissertation, Grenoble Alpes. Accessed July 15, 2019. http://www.theses.fr/2015GREAI064.

MLA Handbook (7th Edition):

Laureau, Axel. “Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters.” 2015. Web. 15 Jul 2019.

Vancouver:

Laureau A. Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres cinétiques effectifs : Development of neutronic models for the thermalhydraulics coupling of the MSFR and the calculation of effective kinetic parameters. [Internet] [Doctoral dissertation]. Grenoble Alpes; 2015. [cited 2019 Jul 15]. Available from: http://www.theses.fr/2015GREAI064.

Council of Science Editors:

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

11. Skwarcan-Bidakowski, Alexander. Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations.

Degree: 2017, Institutionen för Reaktorfysik

A detailed reactor core modeling of the LOVIISA-2 PWR and FORSMARK-3BWR was performed in the Serpent 2 Continuous Energy Monte-Carlocode.Both models of the reactors… (more)

Subjects/Keywords: Nuclear; Reactor; Physics; simulation; FANCSEE; Serpent; energy; neutron; cross; section; Bateman; atom; isotope; fission; reaction; uranium; plutonium; capture; physics; power; calculation; burnup; Kärnkraft; Reaktor; Kärna; Simulering; FANCSEE; uran; pluton; Serpent; energi; atom; isotop; fisson; Bateman; Energy Systems; Energisystem

…Tekniska högskolan – Nuclear Reactor Physics, 2016. [4] http://www.nuclear-power.net… …5 Theory The theory of the nuclear reactor is based on just a few basic concepts, one… …fission fragments that stands for the majority of the power generated by a nuclear reactor. The… …isotope concentration in a nuclear reactor. It is a mathematical model describing the decay… …nuclear age, but have been improved significantly since then. The LOVIISA-2 reactor in Finland… 

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APA (6th Edition):

Skwarcan-Bidakowski, A. (2017). Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations. (Thesis). Institutionen för Reaktorfysik. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260

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):

Skwarcan-Bidakowski, Alexander. “Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations.” 2017. Thesis, Institutionen för Reaktorfysik. Accessed July 15, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260.

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

MLA Handbook (7th Edition):

Skwarcan-Bidakowski, Alexander. “Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations.” 2017. Web. 15 Jul 2019.

Vancouver:

Skwarcan-Bidakowski A. Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations. [Internet] [Thesis]. Institutionen för Reaktorfysik; 2017. [cited 2019 Jul 15]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260.

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

Council of Science Editors:

Skwarcan-Bidakowski A. Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations. [Thesis]. Institutionen för Reaktorfysik; 2017. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260

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

12. Prajapati, Paresh M. Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;.

Degree: Physics, 2012, Maharaja Sayajirao University of Baroda

None

Summary p. 173-177 and References included in chapters

Advisors/Committee Members: Mukherjee, Surjit.

Subjects/Keywords: Physics; Nuclear reaction; Fusion reaction; ADS applications; Solid State Nuclear Track Detector; Advanced Heavy Water Reactor

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APA (6th Edition):

Prajapati, P. M. (2012). Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;. (Thesis). Maharaja Sayajirao University of Baroda. Retrieved from http://shodhganga.inflibnet.ac.in/handle/10603/7492

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):

Prajapati, Paresh M. “Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;.” 2012. Thesis, Maharaja Sayajirao University of Baroda. Accessed July 15, 2019. http://shodhganga.inflibnet.ac.in/handle/10603/7492.

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

MLA Handbook (7th Edition):

Prajapati, Paresh M. “Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;.” 2012. Web. 15 Jul 2019.

Vancouver:

Prajapati PM. Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;. [Internet] [Thesis]. Maharaja Sayajirao University of Baroda; 2012. [cited 2019 Jul 15]. Available from: http://shodhganga.inflibnet.ac.in/handle/10603/7492.

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

Council of Science Editors:

Prajapati PM. Studies of neutron induced fission and nuclear reaction for AHWR and ADS applications;. [Thesis]. Maharaja Sayajirao University of Baroda; 2012. Available from: http://shodhganga.inflibnet.ac.in/handle/10603/7492

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


McMaster University

13. 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 15, 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. 15 Jul 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/11375/22194.

Council of Science Editors:

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


McMaster University

14. 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 July 15, 2019. http://hdl.handle.net/11375/22064.

MLA Handbook (7th Edition):

Sharpe, Jason. “Innovative Analysis Techniques for Canadian SCWR Neutronics.” 2017. Web. 15 Jul 2019.

Vancouver:

Sharpe J. Innovative Analysis Techniques for Canadian SCWR Neutronics. [Internet] [Doctoral dissertation]. McMaster University; 2017. [cited 2019 Jul 15]. 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


McMaster University

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

Degree: PhD, 2018, McMaster University

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Doctoral Dissertation, McMaster University. Accessed July 15, 2019. http://hdl.handle.net/11375/22886.

MLA Handbook (7th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Web. 15 Jul 2019.

Vancouver:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/11375/22886.

Council of Science Editors:

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


McMaster University

16. 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 15, 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. 15 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 15]. 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

17. 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 15, 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. 15 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 15]. 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

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

Degree: PhD, 2011, McMaster University

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Doctoral Dissertation, McMaster University. Accessed July 15, 2019. http://hdl.handle.net/11375/11609.

MLA Handbook (7th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Web. 15 Jul 2019.

Vancouver:

Ball MR. Uncertainty Analysis In Lattice Reactor Physics Calculations. [Internet] [Doctoral dissertation]. McMaster University; 2011. [cited 2019 Jul 15]. Available from: http://hdl.handle.net/11375/11609.

Council of Science Editors:

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


McMaster University

19. 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 15, 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. 15 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 15]. 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


McMaster University

20. 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 15, 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. 15 Jul 2019.

Vancouver:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 Jul 15]. 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


Missouri University of Science and Technology

21. 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 15, 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. 15 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 15]. 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.


Missouri University of Science and Technology

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

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

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

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

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APA (6th Edition):

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

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

Chicago Manual of Style (16th Edition):

Jaradat, Safwan Qasim Mohammad. “Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle.” Doctoral Dissertation, Missouri University of Science and Technology. Accessed July 15, 2019. http://scholarsmine.mst.edu/doctoral_dissertations/2448.

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

MLA Handbook (7th Edition):

Jaradat, Safwan Qasim Mohammad. “Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle.” Web. 15 Jul 2019.

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

Vancouver:

Jaradat SQM. Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle. [Internet] [Doctoral dissertation]. Missouri University of Science and Technology; [cited 2019 Jul 15]. Available from: http://scholarsmine.mst.edu/doctoral_dissertations/2448.

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

Council of Science Editors:

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

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


North Carolina State University

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

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

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

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

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APA (6th Edition):

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

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

Chicago Manual of Style (16th Edition):

Wieselquist, William Adam. “The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE.” 2005. Thesis, North Carolina State University. Accessed July 15, 2019. http://www.lib.ncsu.edu/resolver/1840.16/1861.

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

MLA Handbook (7th Edition):

Wieselquist, William Adam. “The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE.” 2005. Web. 15 Jul 2019.

Vancouver:

Wieselquist WA. The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE. [Internet] [Thesis]. North Carolina State University; 2005. [cited 2019 Jul 15]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/1861.

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

Council of Science Editors:

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

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


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 July 15, 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. 15 Jul 2019.

Vancouver:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Jul 15]. 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

25. 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 15, 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. 15 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 15]. 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


The Ohio State University

26. 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 July 15, 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. 15 Jul 2019.

Vancouver:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Internet] [Doctoral dissertation]. The Ohio State University; 2011. [cited 2019 Jul 15]. 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


The Ohio State University

27. 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 15, 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. 15 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 15]. 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

28. 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 15, 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. 15 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 15]. 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


The Ohio State University

29. 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 15, 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. 15 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 15]. 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


University of California – Irvine

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

Degree: Physics, 2018, University of California – Irvine

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

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

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APA (6th Edition):

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

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

Chicago Manual of Style (16th Edition):

Heckmaier, Elizabeth Klara Marie. “Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy.” 2018. Thesis, University of California – Irvine. Accessed July 15, 2019. http://www.escholarship.org/uc/item/7rd5f743.

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

MLA Handbook (7th Edition):

Heckmaier, Elizabeth Klara Marie. “Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy.” 2018. Web. 15 Jul 2019.

Vancouver:

Heckmaier EKM. Addressing the Reactor Antineutrino Anomaly with a New Detector Array for Fission Fragment Beta-Spectroscopy. [Internet] [Thesis]. University of California – Irvine; 2018. [cited 2019 Jul 15]. Available from: http://www.escholarship.org/uc/item/7rd5f743.

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

Council of Science Editors:

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

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

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