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You searched for subject:(FRAPCON). Showing records 1 – 10 of 10 total matches.

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Texas A&M University

1. Neptune, Kaleb Todd. THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.

Degree: MS, Nuclear Engineering, 2018, Texas A&M University

 In this study, the metazoan parasites of three species of freshwater turtles (the spiny softshell, Apalone spinifera, the common snapping turtle, Chelydra serpentina, and the… (more)

Subjects/Keywords: BISON; RELAP5-3D; FRAPCON

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APA (6th Edition):

Neptune, K. T. (2018). THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174119

Chicago Manual of Style (16th Edition):

Neptune, Kaleb Todd. “THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.” 2018. Masters Thesis, Texas A&M University. Accessed April 18, 2021. http://hdl.handle.net/1969.1/174119.

MLA Handbook (7th Edition):

Neptune, Kaleb Todd. “THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.” 2018. Web. 18 Apr 2021.

Vancouver:

Neptune KT. THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Apr 18]. Available from: http://hdl.handle.net/1969.1/174119.

Council of Science Editors:

Neptune KT. THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174119

2. Daniel de Souza Gomes. Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico.

Degree: 2014, University of São Paulo

A causa imediata do acidente na usina nuclear de Fukushima Daiichi de março de 2011 foi o derretimento do núcleo do reator. Durante este processo,… (more)

Subjects/Keywords: aço-348; FRAPCON; FRAPTRAN; FRAPCON; FRAPTRAN; steel-348

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APA (6th Edition):

Gomes, D. d. S. (2014). Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-19032014-155135/

Chicago Manual of Style (16th Edition):

Gomes, Daniel de Souza. “Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico.” 2014. Doctoral Dissertation, University of São Paulo. Accessed April 18, 2021. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-19032014-155135/.

MLA Handbook (7th Edition):

Gomes, Daniel de Souza. “Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico.” 2014. Web. 18 Apr 2021.

Vancouver:

Gomes DdS. Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico. [Internet] [Doctoral dissertation]. University of São Paulo; 2014. [cited 2021 Apr 18]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-19032014-155135/.

Council of Science Editors:

Gomes DdS. Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico. [Doctoral Dissertation]. University of São Paulo; 2014. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-19032014-155135/

3. Raphael Mejias Dias. Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada.

Degree: 2016, University of São Paulo

Este trabalho tem como objetivo estudar as modificações introduzidas, ao longo de sucessivas versões, nos modelos empíricos do programa computacional FRAPCON utilizado para a simulação… (more)

Subjects/Keywords: alta queima; combustível nuclear; FRAPCON; FRAPCON; high burnup; nuclear fuel

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APA (6th Edition):

Dias, R. M. (2016). Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08062016-134553/

Chicago Manual of Style (16th Edition):

Dias, Raphael Mejias. “Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada.” 2016. Masters Thesis, University of São Paulo. Accessed April 18, 2021. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08062016-134553/.

MLA Handbook (7th Edition):

Dias, Raphael Mejias. “Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada.” 2016. Web. 18 Apr 2021.

Vancouver:

Dias RM. Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada. [Internet] [Masters thesis]. University of São Paulo; 2016. [cited 2021 Apr 18]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08062016-134553/.

Council of Science Editors:

Dias RM. Estudo de modelos para o comportamento a altas queimas de varetas combustíveis de reatores a água leve pressurizada. [Masters Thesis]. University of São Paulo; 2016. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08062016-134553/


Penn State University

4. Bratton, Ryan Nathaniel. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.

Degree: 2015, Penn State University

 The bias and uncertainty in fuel isotopic calculations for a well-defined radiochemical assay benchmark are investigated with Sampler, the new sampling-based uncertainty quantification tool in… (more)

Subjects/Keywords: SCALE; FRAPCON; rod internal pressure; fuel isotopics; spent nuclear fuel

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APA (6th Edition):

Bratton, R. N. (2015). Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27289

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):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Thesis, Penn State University. Accessed April 18, 2021. https://submit-etda.libraries.psu.edu/catalog/27289.

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

MLA Handbook (7th Edition):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Web. 18 Apr 2021.

Vancouver:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Apr 18]. Available from: https://submit-etda.libraries.psu.edu/catalog/27289.

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

Council of Science Editors:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27289

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


University of Tennessee – Knoxville

5. Phillippe, Aaron Martin. A Validation Study of the AMP Nuclear Fuel Performance Code.

Degree: MS, Nuclear Engineering, 2012, University of Tennessee – Knoxville

  The Advanced Multi-Physics (AMP) Fuel Performance Code is a fully coupled, 3-dimensional (3D) code currently in development at the Oak Ridge National Laboratory (ORNL)… (more)

Subjects/Keywords: Halden; IFA; IFPE; FRAPCON; NEAMS; MultiPhysics; Computational Engineering; Nuclear Engineering

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APA (6th Edition):

Phillippe, A. M. (2012). A Validation Study of the AMP Nuclear Fuel Performance Code. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/1314

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):

Phillippe, Aaron Martin. “A Validation Study of the AMP Nuclear Fuel Performance Code.” 2012. Thesis, University of Tennessee – Knoxville. Accessed April 18, 2021. https://trace.tennessee.edu/utk_gradthes/1314.

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

MLA Handbook (7th Edition):

Phillippe, Aaron Martin. “A Validation Study of the AMP Nuclear Fuel Performance Code.” 2012. Web. 18 Apr 2021.

Vancouver:

Phillippe AM. A Validation Study of the AMP Nuclear Fuel Performance Code. [Internet] [Thesis]. University of Tennessee – Knoxville; 2012. [cited 2021 Apr 18]. Available from: https://trace.tennessee.edu/utk_gradthes/1314.

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

Council of Science Editors:

Phillippe AM. A Validation Study of the AMP Nuclear Fuel Performance Code. [Thesis]. University of Tennessee – Knoxville; 2012. Available from: https://trace.tennessee.edu/utk_gradthes/1314

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


University of South Carolina

6. Carroll, Spencer. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.

Degree: MS, Nuclear Engineering, 2014, University of South Carolina

  As current reactors approach the end of their operable lifetime, new reactors are needed if nuclear power is to continue being generated in the… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Implementation; Evaluation; Fuel Creep; Light-Water; FRAPCON

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APA (6th Edition):

Carroll, S. (2014). Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/3581

Chicago Manual of Style (16th Edition):

Carroll, Spencer. “Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.” 2014. Masters Thesis, University of South Carolina. Accessed April 18, 2021. https://scholarcommons.sc.edu/etd/3581.

MLA Handbook (7th Edition):

Carroll, Spencer. “Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.” 2014. Web. 18 Apr 2021.

Vancouver:

Carroll S. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. [Internet] [Masters thesis]. University of South Carolina; 2014. [cited 2021 Apr 18]. Available from: https://scholarcommons.sc.edu/etd/3581.

Council of Science Editors:

Carroll S. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. [Masters Thesis]. University of South Carolina; 2014. Available from: https://scholarcommons.sc.edu/etd/3581


University of South Carolina

7. Porter, Ian Edward. System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios.

Degree: PhD, Nuclear Engineering, 2014, University of South Carolina

  A nuclear reactor systems code has the ability to model the system response in an accident scenario based on known initial conditions at the… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Applied sciences; Frapcon; Fraptran; Fuel dispersal; Fuel performance; Loca; Trace

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APA (6th Edition):

Porter, I. E. (2014). System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios. (Doctoral Dissertation). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/3362

Chicago Manual of Style (16th Edition):

Porter, Ian Edward. “System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios.” 2014. Doctoral Dissertation, University of South Carolina. Accessed April 18, 2021. https://scholarcommons.sc.edu/etd/3362.

MLA Handbook (7th Edition):

Porter, Ian Edward. “System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios.” 2014. Web. 18 Apr 2021.

Vancouver:

Porter IE. System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios. [Internet] [Doctoral dissertation]. University of South Carolina; 2014. [cited 2021 Apr 18]. Available from: https://scholarcommons.sc.edu/etd/3362.

Council of Science Editors:

Porter IE. System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios. [Doctoral Dissertation]. University of South Carolina; 2014. Available from: https://scholarcommons.sc.edu/etd/3362


Penn State University

8. Ozdemir Yilmaz, Mine. Development of Burnup Dependent Fuel Rod Model in Cobra-tf.

Degree: 2014, Penn State University

 The purpose of this research was to develop a burnup dependent fuel thermal conductivity model within Pennsylvania State University, Reactor Dynamics and Fuel Management Group… (more)

Subjects/Keywords: COBRA-TF; CTF; FRAPCON; FRAPTRAN; subchannel; fuel performance; thermal conductivity degradation; TCD; REA; Halden; fuel centerline temperature; MATPRO

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APA (6th Edition):

Ozdemir Yilmaz, M. (2014). Development of Burnup Dependent Fuel Rod Model in Cobra-tf. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/23539

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):

Ozdemir Yilmaz, Mine. “Development of Burnup Dependent Fuel Rod Model in Cobra-tf.” 2014. Thesis, Penn State University. Accessed April 18, 2021. https://submit-etda.libraries.psu.edu/catalog/23539.

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

MLA Handbook (7th Edition):

Ozdemir Yilmaz, Mine. “Development of Burnup Dependent Fuel Rod Model in Cobra-tf.” 2014. Web. 18 Apr 2021.

Vancouver:

Ozdemir Yilmaz M. Development of Burnup Dependent Fuel Rod Model in Cobra-tf. [Internet] [Thesis]. Penn State University; 2014. [cited 2021 Apr 18]. Available from: https://submit-etda.libraries.psu.edu/catalog/23539.

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

Council of Science Editors:

Ozdemir Yilmaz M. Development of Burnup Dependent Fuel Rod Model in Cobra-tf. [Thesis]. Penn State University; 2014. Available from: https://submit-etda.libraries.psu.edu/catalog/23539

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


University of South Carolina

9. Li, Bo-Shiuan. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.

Degree: MS, Nuclear Engineering, 2013, University of South Carolina

  Ceramic materials such as silicon carbide (SiC) are promising candidate materials for nuclear fuel cladding and are of interest as part of a potential… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Accident tolerant fuel; ceramic cladding; FRAPCON; Fuel performance code; Pellet cladding mechanical interactions; Silicon carbide

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APA (6th Edition):

Li, B. (2013). Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/2366

Chicago Manual of Style (16th Edition):

Li, Bo-Shiuan. “Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.” 2013. Masters Thesis, University of South Carolina. Accessed April 18, 2021. https://scholarcommons.sc.edu/etd/2366.

MLA Handbook (7th Edition):

Li, Bo-Shiuan. “Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.” 2013. Web. 18 Apr 2021.

Vancouver:

Li B. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. [Internet] [Masters thesis]. University of South Carolina; 2013. [cited 2021 Apr 18]. Available from: https://scholarcommons.sc.edu/etd/2366.

Council of Science Editors:

Li B. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. [Masters Thesis]. University of South Carolina; 2013. Available from: https://scholarcommons.sc.edu/etd/2366


Penn State University

10. Raja, Faisal Z. DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP.

Degree: 2016, Penn State University

 Having the ability to predict fuel temperatures for efficient multi-physics depletion and transient calculations with reasonable accuracy without the added burden of prohibitively expensive computation… (more)

Subjects/Keywords: COBRA-TF; CTF; FRAPCON; BISON; GAP CONDUCTANCE; REACTOR POWER; FUEL BURNUP; FUEL EXPOSURE; NUCLEAR; FUEL ROD; SUBCHANNEL CODE; FUEL CENTERLINE TEMPERATURE; FUEL SURFACE TEMPERATURE; UO2; ZIRC4; ZIRC CLADDING; LIGHT WATER REACTOR

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APA (6th Edition):

Raja, F. Z. (2016). DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/13509fzr100

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):

Raja, Faisal Z. “DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP.” 2016. Thesis, Penn State University. Accessed April 18, 2021. https://submit-etda.libraries.psu.edu/catalog/13509fzr100.

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

MLA Handbook (7th Edition):

Raja, Faisal Z. “DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP.” 2016. Web. 18 Apr 2021.

Vancouver:

Raja FZ. DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP. [Internet] [Thesis]. Penn State University; 2016. [cited 2021 Apr 18]. Available from: https://submit-etda.libraries.psu.edu/catalog/13509fzr100.

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

Council of Science Editors:

Raja FZ. DEVELOPMENT AND INTEGRATION OF FUEL ROD GAS GAP CONDUCTANCE MODEL IN CTF AS A FUNCTION OF REACTOR POWER AND BURNUP. [Thesis]. Penn State University; 2016. Available from: https://submit-etda.libraries.psu.edu/catalog/13509fzr100

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

.