The Thorium fuel cycle in nuclear reactors
This thesis explores the potential of thorium-based nuclear fuels in Pressurized Water Reactors (PWRs), focusing on the thorium fuel cycle and its various implementations. The research investigates the benefits and challenges associated with thorium fuel, including its higher conversion ratios, impr...
- Autores:
-
García Eslava, Frank Worman
- Tipo de recurso:
- Trabajo de grado de pregrado
- Fecha de publicación:
- 2024
- Institución:
- Universidad de los Andes
- Repositorio:
- Séneca: repositorio Uniandes
- Idioma:
- eng
- OAI Identifier:
- oai:repositorio.uniandes.edu.co:1992/75840
- Acceso en línea:
- https://hdl.handle.net/1992/75840
- Palabra clave:
- Thorium fuel cycle
Pressurized Water Reactor
Uranium-233
Nuclear fuel
Re- actor simulation
OpenMC
Sustainable energy
Thorium Molten Salt Reactors
Ciclo del combustible de torio
Reactor de Agua Presurizada
Uranio-233
Combustible nuclear
Simulación de reactores
Energı́a sostenible
Reactores de Sales Fundidas de Torio
Física
- Rights
- openAccess
- License
- https://repositorio.uniandes.edu.co/static/pdf/aceptacion_uso_es.pdf
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| dc.title.eng.fl_str_mv |
The Thorium fuel cycle in nuclear reactors |
| dc.title.alternative.spa.fl_str_mv |
Reactores Nucleares Basados en el Ciclo de Combustible del Torio |
| title |
The Thorium fuel cycle in nuclear reactors |
| spellingShingle |
The Thorium fuel cycle in nuclear reactors Thorium fuel cycle Pressurized Water Reactor Uranium-233 Nuclear fuel Re- actor simulation OpenMC Sustainable energy Thorium Molten Salt Reactors Ciclo del combustible de torio Reactor de Agua Presurizada Uranio-233 Combustible nuclear Simulación de reactores Energı́a sostenible Reactores de Sales Fundidas de Torio Física |
| title_short |
The Thorium fuel cycle in nuclear reactors |
| title_full |
The Thorium fuel cycle in nuclear reactors |
| title_fullStr |
The Thorium fuel cycle in nuclear reactors |
| title_full_unstemmed |
The Thorium fuel cycle in nuclear reactors |
| title_sort |
The Thorium fuel cycle in nuclear reactors |
| dc.creator.fl_str_mv |
García Eslava, Frank Worman |
| dc.contributor.advisor.none.fl_str_mv |
Sanabria Arenas, Juan Carlos |
| dc.contributor.author.none.fl_str_mv |
García Eslava, Frank Worman |
| dc.contributor.jury.none.fl_str_mv |
Hernández Pico, Yenny Rocio |
| dc.subject.keyword.eng.fl_str_mv |
Thorium fuel cycle |
| topic |
Thorium fuel cycle Pressurized Water Reactor Uranium-233 Nuclear fuel Re- actor simulation OpenMC Sustainable energy Thorium Molten Salt Reactors Ciclo del combustible de torio Reactor de Agua Presurizada Uranio-233 Combustible nuclear Simulación de reactores Energı́a sostenible Reactores de Sales Fundidas de Torio Física |
| dc.subject.keyword.none.fl_str_mv |
Pressurized Water Reactor Uranium-233 Nuclear fuel Re- actor simulation OpenMC Sustainable energy Thorium Molten Salt Reactors Ciclo del combustible de torio Reactor de Agua Presurizada Uranio-233 Combustible nuclear Simulación de reactores Energı́a sostenible Reactores de Sales Fundidas de Torio |
| dc.subject.themes.spa.fl_str_mv |
Física |
| description |
This thesis explores the potential of thorium-based nuclear fuels in Pressurized Water Reactors (PWRs), focusing on the thorium fuel cycle and its various implementations. The research investigates the benefits and challenges associated with thorium fuel, including its higher conversion ratios, improved thermal properties, and intrinsic proliferation resistance. The study includes detailed simulations using OpenMC to analyze the behavior of thorium oxide (ThOX) with uranium-233 (233 U ) at different concentrations. The results demonstrate that while thorium-based fuels can achieve breeding, maintaining criticality presents challenges. The thesis also examines the impact of fuel composition and concentration on reactor performance and safety. The findings suggest that optimizing these parameters is crucial for enhancing the performance and safety of thorium-based fuels. The research concludes with a discussion on the future prospects of thorium in the nuclear industry and the need for further research and development to fully realize its potential as a sustainable nuclear fuel. |
| publishDate |
2024 |
| dc.date.issued.none.fl_str_mv |
2024-12-09 |
| dc.date.accessioned.none.fl_str_mv |
2025-01-30T15:38:23Z |
| dc.date.available.none.fl_str_mv |
2025-01-30T15:38:23Z |
| dc.type.none.fl_str_mv |
Trabajo de grado - Pregrado |
| dc.type.driver.none.fl_str_mv |
info:eu-repo/semantics/bachelorThesis |
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info:eu-repo/semantics/acceptedVersion |
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http://purl.org/coar/resource_type/c_7a1f |
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eng |
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eng |
| dc.relation.references.none.fl_str_mv |
T. J. Dolan, Molten Salt Reactors and Thorium Energy, 1st ed., Woodhead Publishing, 2017. ISBN: 9780081011263. J. R. Lamarsh y A. J. Baratta, Introduction to nuclear engineering, Prentice Hall; Pearson Education distributor, 2009. K. Kornecki y C. F. Wise, "The role of advanced nuclear reactors and fuel cycles in a future energy system," PNAS Nexus, vol. 3, n.º 2, enero 2024. DOI: 10.1093/pnasnexus/pgae030. E. E. Lewis, Fundamentals of Nuclear Reactor Physics, Elsevier e-books, Amsterdam, 2014. W. M. Stacey, Nuclear reactor physics, Wiley-VCH-Verl, Weinheim, 2010. J.-L. Basdevant, J. Rich y M. Spiro, Fundamentals in nuclear physics: from nuclear structure to cosmology, 1st ed., Springer, 2005. ISBN: 9780387016726. K. S. Krane, Introductory Nuclear Physics, 2nd ed., John Wiley, 1988. ISBN: 9780471805533. International Atomic Energy Agency, Thorium Fuel Cycle — Potential Benefits and Challenges, IAEA-TECDOC-1450, Vienna, Austria, 2005. ISBN: 92-0-103405-9. URL: https://www.iaea.org/publications/7196/thorium-fuel-cycle-potential-benefits-and-challenges. A. Asghari, "The Water Neutron Detector (WaND)," 2016. URL: https://api.semanticscholar.org/CorpusID:100282839. National Nuclear Data Center, "National Nuclear Data Center," 2024. URL: https://www.nndc.bnl.gov/. Accessed: 2024-08-24. J. C. Sanabria, "Reactores nucleares - Notas de clase," 2021. Unpublished. P. Mohanakrishnan (editor), O. P. Singh (editor) y K. Umasankari (editor), Physics of Nuclear Reactors, 1st ed., Academic Press, 2021. ISBN: 9780128224410. B. S. Tomar, P. R. Vasudeva Rao, S. B. Roy, J. P. Panakkal, K. Raj y A. N. Nandakumar, Nuclear Fuel Cycle, Springer, 2023. ISBN: 9789819909483. E. E. Lewis, Fundamentals of Nuclear Reactor Physics, Academic Press, 2008. ISBN: 9780123706317. U. E. Humphrey y M. U. Khandaker, "Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects," Renewable and Sustainable Energy Reviews, vol. 97, págs. 259-275, 2018. DOI: https://doi.org/10.1016/j.rser.2018.08.019. URL: https://www.sciencedirect.com/science/article/pii/S1364032118305951. INTERNATIONAL ATOMIC ENERGY AGENCY, Thorium Fuel Cycle - Potential Benefits and Challenges, TECDOC Series, n.º 1450, Vienna, 2005. ISBN: 92-0-103405-9. URL: https://www.iaea.org/publications/7192/thorium-fuel-cycle-potential-benefits-and-challenges. Servicio Geológico Colombiano, "Atlas Geoquímico de Colombia: Concentración de Torio (Th)," Bogotá: Servicio Geológico Colombiano, versión 2020. URL: https://www.sgc.gov.co. Deutsches Institut für Normung e.V. (DIN), "Measurement of radioactivity in the environment - Air: radon-222 Pt 11: Test method for soil gas with sampling at depth (ISO 11665-11:2016); German version EN ISO 11665-11:2019," Beuth Verlag, Berlin, Germany, 2020. Haynes International Inc., "Nickel Alloy Brochure," 2024. URL: https://haynesintl.com/wp-content/uploads/2024/05/n-brochure.pdf. Accessed: 2024-10-07. D. A. Andersson, C. R. Stanek, C. Matthews y otros, "The past, present, and future of nuclear fuel," MRS Bulletin, vol. 48, págs. 1154-1162, 2023. DOI: 10.1557/s43577-023-00631-3. URL: https://doi.org/10.1557/s43577-023-00631-3. INTERNATIONAL ATOMIC ENERGY AGENCY, Performance Analysis Review of Thorium TRISO Coated Particles During Manufacture, Irradiation and Accident Condition Heating Tests, TECDOC Series, n.º 1761, Vienna, 2015. ISBN: 978-92-0-100715-5. URL: https://www.iaea.org/publications/10844/performance-analysis-review-of-thorium-triso-coated-particles-during-manufacture-irradiation-and-accident-condition-heating-tests. H. Xu, "The Development of TMSR Technology in China," 2017. URL: https://www.gen-4.org/gif/upload/docs/application/pdf/2017-05/03_hongjie_xu_china.pdf. Accessed: 2024-10-07. P. V. Achuthan y A. Ramanujam, "Aqueous Reprocessing by THOREX Process," en Thoria-based Nuclear Fuels: Thermophysical and Thermodynamic Properties, Fabrication, Reprocessing, and Waste Management, eds. D. Das y S. R. Bharadwaj, Springer London, London, 2013, págs. 279-333. I. Pázsit, A. Jonsson y L. Pál, "Analytical solutions of the molten salt reactor equations," Annals of Nuclear Energy, vol. 50, págs. 206-214, 2012. DOI: https://doi.org/10.1016/j.anucene.2012.05.037. URL: https://www.sciencedirect.com/science/article/pii/S030645491200237X. P. K. Romano, N. E. Horelik, B. R. Herman, A. G. Nelson, B. Forget y K. Smith, "OpenMC: A state-of-the-art Monte Carlo code for research and development," Annals of Nuclear Energy, vol. 82, págs. 90-97, 2015. DOI: https://doi.org/10.1016/j.anucene.2014.07.048. URL: https://www.sciencedirect.com/science/article/pii/S030645491400379X. C. Josey, B. Forget y K. Smith, "High order methods for the integration of the Bateman equations and other problems of the form of y=F(y,t)y," Journal of Computational Physics, vol. 350, págs. 296-313, 2017. DOI: https://doi.org/10.1016/j.jcp.2017.08.025. URL: https://www.sciencedirect.com/science/article/pii/S002199911730596X. The OpenMC Development Team, "OpenMC Documentation," 2024. URL: https://docs.openmc.org/en/stable/. Accessed: 2024-10-07. The HDF Group, "HDF5 Documentation," 2024. URL: https://support.hdfgroup.org/documentation/. Accessed: 2024-10-07. C. W. Lau, C. Demazière, H. Nylén y U. Sandberg, "Improvement of LWR thermal margins by introducing thorium," Progress in Nuclear Energy, vol. 61, págs. 48-56, 2012. DOI: https://doi.org/10.1016/j.pnucene.2012.07.004. URL: https://www.sciencedirect.com/science/article/pii/S0149197012000972. S. Si, "Roadmap Design for Thorium-Uranium Breeding Recycle in PWR," International Atomic Energy Agency (IAEA), Vienna, Austria, 2011. C. W. Lau, C. Demazière, H. Nylén y U. Sandberg, "Improvement of LWR thermal margins by introducing thorium," Progress in Nuclear Energy, vol. 61, págs. 48-56, 2012. DOI: https://doi.org/10.1016/j.pnucene.2012.07.004. URL: https://www.sciencedirect.com/science/article/pii/S0149197012000972. A. F. Porras-Ríos y J. de J. Díaz-Velásquez, "El uranio como recurso energético y su actualidad minera en Colombia," DYNA, vol. 86, n.º 208, págs. 362-367. NEA, Uranium 2011: Resources, Production and Demand, OECD Publishing, Paris, 2012. |
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Sanabria Arenas, Juan Carlosvirtual::22757-1García Eslava, Frank WormanHernández Pico, Yenny Rociovirtual::22758-12025-01-30T15:38:23Z2025-01-30T15:38:23Z2024-12-09https://hdl.handle.net/1992/75840instname:Universidad de los Andesreponame:Repositorio Institucional Sénecarepourl:https://repositorio.uniandes.edu.co/This thesis explores the potential of thorium-based nuclear fuels in Pressurized Water Reactors (PWRs), focusing on the thorium fuel cycle and its various implementations. The research investigates the benefits and challenges associated with thorium fuel, including its higher conversion ratios, improved thermal properties, and intrinsic proliferation resistance. The study includes detailed simulations using OpenMC to analyze the behavior of thorium oxide (ThOX) with uranium-233 (233 U ) at different concentrations. The results demonstrate that while thorium-based fuels can achieve breeding, maintaining criticality presents challenges. The thesis also examines the impact of fuel composition and concentration on reactor performance and safety. The findings suggest that optimizing these parameters is crucial for enhancing the performance and safety of thorium-based fuels. The research concludes with a discussion on the future prospects of thorium in the nuclear industry and the need for further research and development to fully realize its potential as a sustainable nuclear fuel.Esta tesis explora el potencial de los combustibles nucleares basados en torio en los Reactores de Agua Presurizada (PWRs), enfocándose en el ciclo del combustible de torio y sus diversas implementaciones. El proyecto investiga los beneficios y desafíos asociados con el combustible de torio, incluyendo sus mayores ratios de conversión, mejores propiedades térmicas y resistencia intrı́nseca a la proliferación. El estudio incluye simulaciones detalladas utilizando OpenMC para analizar el comportamiento del óxido de torio (ThOX) con uranio-233 (233 U ) en diferentes concentraciones. Los resultados demuestran que, aunque los combustibles basados en torio pueden lograr tasas de producción de isotopos fisiles positivas, mantener la criticidad presenta desafı́os. La tesis también examina el impacto de la composición y concentración del combustible en el rendimiento y la seguridad del reactor. Los hallazgos sugieren que optimizar estos parámetros es crucial para mejorar el rendimiento y la seguridad de los combustibles basados en torio. La investigación concluye con una discusión sobre las perspectivas futuras del torio en la industria nuclear y la necesidad de más investigación y desarrollo para realizar plenamente su potencial como un combustible nuclear sostenible.Pregrado113 páginasapplication/pdfengUniversidad de los AndesFísicaFacultad de CienciasDepartamento de Físicahttps://repositorio.uniandes.edu.co/static/pdf/aceptacion_uso_es.pdfinfo:eu-repo/semantics/openAccesshttp://purl.org/coar/access_right/c_abf2The Thorium fuel cycle in nuclear reactorsReactores Nucleares Basados en el Ciclo de Combustible del TorioTrabajo de grado - Pregradoinfo:eu-repo/semantics/bachelorThesisinfo:eu-repo/semantics/acceptedVersionhttp://purl.org/coar/resource_type/c_7a1fTexthttp://purl.org/redcol/resource_type/TPThorium fuel cyclePressurized Water ReactorUranium-233Nuclear fuelRe- actor simulationOpenMCSustainable energyThorium Molten Salt ReactorsCiclo del combustible de torioReactor de Agua PresurizadaUranio-233Combustible nuclearSimulación de reactoresEnergı́a sostenibleReactores de Sales Fundidas de TorioFísicaT. J. Dolan, Molten Salt Reactors and Thorium Energy, 1st ed., Woodhead Publishing, 2017. ISBN: 9780081011263.J. R. Lamarsh y A. J. Baratta, Introduction to nuclear engineering, Prentice Hall; Pearson Education distributor, 2009.K. Kornecki y C. F. Wise, "The role of advanced nuclear reactors and fuel cycles in a future energy system," PNAS Nexus, vol. 3, n.º 2, enero 2024. DOI: 10.1093/pnasnexus/pgae030.E. E. Lewis, Fundamentals of Nuclear Reactor Physics, Elsevier e-books, Amsterdam, 2014.W. M. Stacey, Nuclear reactor physics, Wiley-VCH-Verl, Weinheim, 2010.J.-L. Basdevant, J. Rich y M. Spiro, Fundamentals in nuclear physics: from nuclear structure to cosmology, 1st ed., Springer, 2005. ISBN: 9780387016726.K. S. Krane, Introductory Nuclear Physics, 2nd ed., John Wiley, 1988. ISBN: 9780471805533.International Atomic Energy Agency, Thorium Fuel Cycle — Potential Benefits and Challenges, IAEA-TECDOC-1450, Vienna, Austria, 2005. ISBN: 92-0-103405-9. URL: https://www.iaea.org/publications/7196/thorium-fuel-cycle-potential-benefits-and-challenges.A. Asghari, "The Water Neutron Detector (WaND)," 2016. URL: https://api.semanticscholar.org/CorpusID:100282839.National Nuclear Data Center, "National Nuclear Data Center," 2024. URL: https://www.nndc.bnl.gov/. Accessed: 2024-08-24.J. C. Sanabria, "Reactores nucleares - Notas de clase," 2021. Unpublished.P. Mohanakrishnan (editor), O. P. Singh (editor) y K. Umasankari (editor), Physics of Nuclear Reactors, 1st ed., Academic Press, 2021. ISBN: 9780128224410.B. S. Tomar, P. R. Vasudeva Rao, S. B. Roy, J. P. Panakkal, K. Raj y A. N. Nandakumar, Nuclear Fuel Cycle, Springer, 2023. ISBN: 9789819909483.E. E. Lewis, Fundamentals of Nuclear Reactor Physics, Academic Press, 2008. ISBN: 9780123706317.U. E. Humphrey y M. U. Khandaker, "Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects," Renewable and Sustainable Energy Reviews, vol. 97, págs. 259-275, 2018. DOI: https://doi.org/10.1016/j.rser.2018.08.019. URL: https://www.sciencedirect.com/science/article/pii/S1364032118305951.INTERNATIONAL ATOMIC ENERGY AGENCY, Thorium Fuel Cycle - Potential Benefits and Challenges, TECDOC Series, n.º 1450, Vienna, 2005. ISBN: 92-0-103405-9. URL: https://www.iaea.org/publications/7192/thorium-fuel-cycle-potential-benefits-and-challenges.Servicio Geológico Colombiano, "Atlas Geoquímico de Colombia: Concentración de Torio (Th)," Bogotá: Servicio Geológico Colombiano, versión 2020. URL: https://www.sgc.gov.co.Deutsches Institut für Normung e.V. (DIN), "Measurement of radioactivity in the environment - Air: radon-222 Pt 11: Test method for soil gas with sampling at depth (ISO 11665-11:2016); German version EN ISO 11665-11:2019," Beuth Verlag, Berlin, Germany, 2020.Haynes International Inc., "Nickel Alloy Brochure," 2024. URL: https://haynesintl.com/wp-content/uploads/2024/05/n-brochure.pdf. Accessed: 2024-10-07.D. A. Andersson, C. R. Stanek, C. Matthews y otros, "The past, present, and future of nuclear fuel," MRS Bulletin, vol. 48, págs. 1154-1162, 2023. DOI: 10.1557/s43577-023-00631-3. URL: https://doi.org/10.1557/s43577-023-00631-3.INTERNATIONAL ATOMIC ENERGY AGENCY, Performance Analysis Review of Thorium TRISO Coated Particles During Manufacture, Irradiation and Accident Condition Heating Tests, TECDOC Series, n.º 1761, Vienna, 2015. ISBN: 978-92-0-100715-5. URL: https://www.iaea.org/publications/10844/performance-analysis-review-of-thorium-triso-coated-particles-during-manufacture-irradiation-and-accident-condition-heating-tests.H. Xu, "The Development of TMSR Technology in China," 2017. URL: https://www.gen-4.org/gif/upload/docs/application/pdf/2017-05/03_hongjie_xu_china.pdf. Accessed: 2024-10-07.P. V. Achuthan y A. Ramanujam, "Aqueous Reprocessing by THOREX Process," en Thoria-based Nuclear Fuels: Thermophysical and Thermodynamic Properties, Fabrication, Reprocessing, and Waste Management, eds. D. Das y S. R. Bharadwaj, Springer London, London, 2013, págs. 279-333.I. Pázsit, A. Jonsson y L. Pál, "Analytical solutions of the molten salt reactor equations," Annals of Nuclear Energy, vol. 50, págs. 206-214, 2012. DOI: https://doi.org/10.1016/j.anucene.2012.05.037. URL: https://www.sciencedirect.com/science/article/pii/S030645491200237X.P. K. Romano, N. E. Horelik, B. R. Herman, A. G. Nelson, B. Forget y K. Smith, "OpenMC: A state-of-the-art Monte Carlo code for research and development," Annals of Nuclear Energy, vol. 82, págs. 90-97, 2015. DOI: https://doi.org/10.1016/j.anucene.2014.07.048. URL: https://www.sciencedirect.com/science/article/pii/S030645491400379X.C. Josey, B. Forget y K. Smith, "High order methods for the integration of the Bateman equations and other problems of the form of y=F(y,t)y," Journal of Computational Physics, vol. 350, págs. 296-313, 2017. DOI: https://doi.org/10.1016/j.jcp.2017.08.025. URL: https://www.sciencedirect.com/science/article/pii/S002199911730596X.The OpenMC Development Team, "OpenMC Documentation," 2024. URL: https://docs.openmc.org/en/stable/. Accessed: 2024-10-07.The HDF Group, "HDF5 Documentation," 2024. URL: https://support.hdfgroup.org/documentation/. Accessed: 2024-10-07.C. W. Lau, C. Demazière, H. Nylén y U. Sandberg, "Improvement of LWR thermal margins by introducing thorium," Progress in Nuclear Energy, vol. 61, págs. 48-56, 2012. DOI: https://doi.org/10.1016/j.pnucene.2012.07.004. URL: https://www.sciencedirect.com/science/article/pii/S0149197012000972.S. Si, "Roadmap Design for Thorium-Uranium Breeding Recycle in PWR," International Atomic Energy Agency (IAEA), Vienna, Austria, 2011.C. W. Lau, C. Demazière, H. Nylén y U. Sandberg, "Improvement of LWR thermal margins by introducing thorium," Progress in Nuclear Energy, vol. 61, págs. 48-56, 2012. DOI: https://doi.org/10.1016/j.pnucene.2012.07.004. URL: https://www.sciencedirect.com/science/article/pii/S0149197012000972.A. F. Porras-Ríos y J. de J. Díaz-Velásquez, "El uranio como recurso energético y su actualidad minera en Colombia," DYNA, vol. 86, n.º 208, págs. 362-367.NEA, Uranium 2011: Resources, Production and Demand, OECD Publishing, Paris, 2012.201912534Publicationhttps://scholar.google.es/citations?user=KXWwfMMAAAAJvirtual::22758-10000-0002-6980-8820virtual::22758-1https://scienti.minciencias.gov.co/cvlac/visualizador/generarCurriculoCv.do?cod_rh=0000008419virtual::22757-1https://scienti.minciencias.gov.co/cvlac/visualizador/generarCurriculoCv.do?cod_rh=0000318566virtual::22758-12e3cac64-ccc2-42c3-b3f9-2ef8e094ba71virtual::22757-12e3cac64-ccc2-42c3-b3f9-2ef8e094ba71virtual::22757-15ec439ad-c826-485e-8b94-d4fe2bfc1017virtual::22758-15ec439ad-c826-485e-8b94-d4fe2bfc1017virtual::22758-1ORIGINALThorium fuel cycle in nuclear reactors.pdfThorium fuel cycle in nuclear reactors.pdfapplication/pdf1393092https://repositorio.uniandes.edu.co/bitstreams/fa8de7c6-3269-4647-87e4-177cd4625ad6/download27d1011045bf45a02c42e3dfab404494MD51autorizacion_tesis_filled.pdfautorizacion_tesis_filled.pdfHIDEapplication/pdf285783https://repositorio.uniandes.edu.co/bitstreams/4c2b5816-bc5d-43c4-ad04-1778181324ab/downloadb7fc8c180fc97fcdea6a307ff5bd9295MD53LICENSElicense.txtlicense.txttext/plain; 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