{"id":973,"date":"2021-05-07T17:48:38","date_gmt":"2021-05-07T15:48:38","guid":{"rendered":"https:\/\/blogs.uned.es\/grupo-afp\/?p=973"},"modified":"2021-05-07T17:59:59","modified_gmt":"2021-05-07T15:59:59","slug":"elementor-973","status":"publish","type":"post","link":"https:\/\/blogs.uned.es\/grupo-afp\/2021\/05\/07\/elementor-973\/","title":{"rendered":"Evoluci\u00f3n con la temperatura de requisitos mec\u00e1nicos de materiales empleados en la fabricaci\u00f3n de equipos a presi\u00f3n para la industria nuclear"},"content":{"rendered":"\t\t
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Evoluci\u00f3n con la temperatura de requisitos mec\u00e1nicos de materiales empleados en la fabricaci\u00f3n de equipos a presi\u00f3n para la industria nuclear<\/a><\/h2>\t\t\t\t<\/div>\n\t\t\t\t<\/div>\n\t\t\t\t\t<\/div>\n\t\t<\/div>\n\t\t\t\t\t<\/div>\n\t\t<\/section>\n\t\t\t\t
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This article presents an analysis, with respect to temperature, of the evolution of requirements of mechanical behavior of materials used in the manufacture of special pressure vessels for the nuclear sector. It has been verified that the evolution described by the KTA and ASME B&PV codes for elastic limit requirements is similar to the adjustment obtained experimentally on specimens from surveillance capsules taken from North American nuclear power plants. Likewise, it has been concluded that the materials forged for use in the manufacture of the reactor vessel, whether they are specified by ASME B&PV or in the KTA standards, must have a mechanical resistance superior to that required for materials manufactured by processes of lamination. Also, the forged material specified by ASME B&PV has a higher resistance to thermal distortion, associated with a higher minimum tensile strength requirement. Finally, it has been confirmed that the elastic limit values specified for the different materials analyzed are sufficient to ensure that deformations will not occur in the plastic region of the material, since according to the calculations made in this work, the membrane stresses in longitudinal and transverse direction they are well below 67% of the elastic limit, according to the safety factor (n = 2\/3) required in ASME B&PV and KTA. \/\/ En este art\u00edculo se presenta un an\u00e1lisis, con respecto a la temperatura, de la evoluci\u00f3n de requisitos de comportamiento mec\u00e1nico de materiales empleados en la fabricaci\u00f3n de recipientes especiales a presi\u00f3n para el sector nuclear. Se ha verificado que la evoluci\u00f3n descrita por los c\u00f3digos KTA y ASME B&PV para requisitos de l\u00edmite el\u00e1stico es similar al ajuste obtenido experimentalmente sobre probetas procedentes de c\u00e1psulas de vigilancia tomadas de centrales nucleares norteamericanas. As\u00ed mismo, se ha podido concluir que los materiales forjados de empleo en la fabricaci\u00f3n de la vasija del reactor, ya se encuentren especificados por ASME B&PV o en las normas KTA, deben presentar una resistencia mec\u00e1nica superior a la requerida para los materiales fabricados mediante procesos de laminaci\u00f3n. Asimismo, el material forjado especificado por ASME B&PV presenta una mayor resistencia a la distorsi\u00f3n t\u00e9rmica, asociada a un mayor requisito m\u00ednimo de resistencia a tracci\u00f3n. Por \u00faltimo, se ha confirmado que los valores de l\u00edmite el\u00e1stico especificados para los distintos materiales analizados son suficientes para asegurar que no se producir\u00e1n deformaciones en la regi\u00f3n pl\u00e1stica del material, ya que de acuerdo con los c\u00e1lculos realizados en este trabajo, los esfuerzos de membrana en direcci\u00f3n longitudinal y transversal se encuentran muy por debajo del 67% del l\u00edmite el\u00e1stico, de acuerdo con el factor de seguridad (n = 2\/3) requerido en ASME B&PV y KTA… See all…<\/strong><\/span><\/a><\/span><\/p>\t\t\t\t\t\t\t\t<\/div>\n\t\t\t\t<\/div>\n\t\t\t\t\t<\/div>\n\t\t<\/div>\n\t\t\t\t\t<\/div>\n\t\t<\/section>\n\t\t\t\t<\/div>\n\t\t","protected":false},"excerpt":{"rendered":"

Evoluci\u00f3n con la temperatura de requisitos mec\u00e1nicos de materiales empleados en la fabricaci\u00f3n de equipos a presi\u00f3n para la industria nuclear This article presents an analysis, with respect to temperature, of the evolution of requirements of mechanical behavior of materials used in the manufacture of special pressure vessels for the nuclear sector. It has been verified that the evolution described by the KTA and ASME B&PV codes for elastic limit requirements is similar to the adjustment obtained experimentally on specimens from surveillance capsules taken from North American nuclear power plants. Likewise, it has been concluded that the materials forged for use in the manufacture of the reactor vessel, whether they are specified by ASME B&PV or in the KTA standards, must have a mechanical resistance superior to that required for materials manufactured by processes of lamination. Also, the forged material specified by ASME B&PV has a higher resistance to thermal…<\/p>\n

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