Desarrollos en métodos y modelos para evaluación de aspectos seguridad nuclear para diseño y licenciamiento de reactores nucleares y casos de aplicación

Desarrollos en métodos y modelos para evaluación de aspectos seguridad nuclear para diseño y licenciamiento de reactores nucleares y casos de aplicación

In this project advances in research and development in methodologies and models for nuclear research and power reactors for safety assessment of the design to support engineering and regulatory licensing processes, are proposed. To address the respective safety assessments, deterministic and probab...

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Detalles Bibliográficos
Autores principales: Aramayo, Cristian Fabián, Astiz, Tomás Eloy, Beretta, Enzo Fabricio, Braida, Iván Rafael, Caputo, Marcelo Alejandro, Catalá, Luis Pedro, Claramonte, Lucas Ezequiel, Domanski, Diana Berenice, García Espiño, Mora Constanza, García, Juan Matías, Gimémez, Marcelo Oscar, Griet, Marcela, Grinberg, Mariela Stella, Hosid, Ariel Martín, López, Cintia Anabel, Maturana, Roberto Hernán, Mezio, Federico Andrés, Mulleady, Cristobal, Quiroga, David Alfredo, Ristoff, María Emilia, Villaverde, María Magdalena, Zanocco, Pablo Gustavo
Publicado: 2019
Materias:
Energía nuclear
Ingeniería nuclear
Reactor nuclear
Seguridad nuclear
Acceso en línea:https://bdigital.uncu.edu.ar/fichas.php?idobjeto=14292
Descripción
Sumario:In this project advances in research and development in methodologies and models for nuclear research and power reactors for safety assessment of the design to support engineering and regulatory licensing processes, are proposed. To address the respective safety assessments, deterministic and probabilistic methodologies will be used in order to identify complementary aspects and achieve a more robust evaluation of the installation. Given the need of CNEA to have updated methodologies and modeling tools to support the engineering and construction projects of RA-10 research reactor and CAREM-25 electric generation prototype reactor, it is also proposed the application of the evaluation models and techniques developed to assist the final licensing process in the RA-10 project, while in the CAREM-25 Project, to support the design process. The objectives are: *to develop new modeling techniques, for example in probabilistic analysis, to address Multiple Units PSA, and in the deterministic analysis, for the treatment of uncertainties in system observables as the functional reliability; * investigate and apply methodologies for the development of Human Factor Engineering in the design of nuclear facilities. *Investigate and develop models of atmospheric dispersion and comprehensive evaluation of the degree of safety of nuclear reactors, under the context of Probabilistic Analysis Level 3; * to develop deterministic and probabilistic models of CAREM reactor and containment and perform safety evaluations applying both methodologies, oriented to the design. Expected results: to obtain advances in safety assessment techniques and methodologies; to develop deterministic and probabilistic models of CAREM and RA-10 reactors, with their corresponding technical reports; to perform safety assessments to support the design of CAREM, and the licensing of RA-10, with their corresponding technical reports.

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