{"id":1193,"date":"2021-05-08T17:57:11","date_gmt":"2021-05-08T15:57:11","guid":{"rendered":"https:\/\/blogs.uned.es\/grupo-afp\/?p=1193"},"modified":"2021-05-08T17:58:27","modified_gmt":"2021-05-08T15:58:27","slug":"elementor-1193","status":"publish","type":"post","link":"https:\/\/blogs.uned.es\/grupo-afp\/2021\/05\/08\/elementor-1193\/","title":{"rendered":"Quantitative model for predicting the suitability of candidate materials for reactor pressure-vessels manufacturing"},"content":{"rendered":"\t\t<div data-elementor-type=\"wp-post\" data-elementor-id=\"1193\" class=\"elementor elementor-1193\">\n\t\t\t\t\t\t<section class=\"elementor-section elementor-top-section elementor-element elementor-element-6f801b4 elementor-section-boxed elementor-section-height-default elementor-section-height-default\" data-id=\"6f801b4\" data-element_type=\"section\" data-e-type=\"section\">\n\t\t\t\t\t\t<div class=\"elementor-container elementor-column-gap-default\">\n\t\t\t\t\t<div class=\"elementor-column elementor-col-100 elementor-top-column elementor-element elementor-element-4cd689e\" data-id=\"4cd689e\" data-element_type=\"column\" data-e-type=\"column\">\n\t\t\t<div class=\"elementor-widget-wrap elementor-element-populated\">\n\t\t\t\t\t\t<div class=\"elementor-element elementor-element-405a1b8 elementor-widget elementor-widget-heading\" data-id=\"405a1b8\" data-element_type=\"widget\" data-e-type=\"widget\" data-widget_type=\"heading.default\">\n\t\t\t\t<div class=\"elementor-widget-container\">\n\t\t\t\t\t<h2 class=\"elementor-heading-title elementor-size-default\"><a href=\"https:\/\/www.researchgate.net\/publication\/318113929_Quantitative_model_for_predicting_the_suitability_of_candidate_materials_for_reactor_pressure-vessels_manufacturing\" target=\"_blank\">Quantitative model for predicting the suitability of candidate materials for reactor pressure-vessels manufacturing<\/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<section class=\"elementor-section elementor-top-section elementor-element elementor-element-6653328 elementor-section-boxed elementor-section-height-default elementor-section-height-default\" data-id=\"6653328\" data-element_type=\"section\" data-e-type=\"section\">\n\t\t\t\t\t\t<div class=\"elementor-container elementor-column-gap-default\">\n\t\t\t\t\t<div class=\"elementor-column elementor-col-100 elementor-top-column elementor-element elementor-element-e0fb4b9\" data-id=\"e0fb4b9\" data-element_type=\"column\" data-e-type=\"column\">\n\t\t\t<div class=\"elementor-widget-wrap elementor-element-populated\">\n\t\t\t\t\t\t<div class=\"elementor-element elementor-element-2a74911 elementor-widget elementor-widget-text-editor\" data-id=\"2a74911\" data-element_type=\"widget\" data-e-type=\"widget\" data-widget_type=\"text-editor.default\">\n\t\t\t\t<div class=\"elementor-widget-container\">\n\t\t\t\t\t\t\t\t\t<p>In this work, an integrative approach that eases the material selection stage is presented. Twenty different specifications of materials from 1st to 4th generation of pressurized water reactors have been analyzed, covering the main designs of pressurized reactors from Western Europe, Japan and Russia. Thus, the results show that steels 15Kh2MFAA, 20MnMoNi55 and SA533 Gr.B Cl.1 are the best material options to prevent the embrittlement induced by radiation&#8230; <a href=\"https:\/\/www.researchgate.net\/publication\/318113929_Quantitative_model_for_predicting_the_suitability_of_candidate_materials_for_reactor_pressure-vessels_manufacturing\" target=\"_blank\" rel=\"noopener\"><span style=\"text-decoration: underline;color: #3366ff\"><strong>See all&#8230;<\/strong><\/span><\/a><\/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":"<p>Quantitative model for predicting the suitability of candidate materials for reactor pressure-vessels manufacturing In this work, an integrative approach that eases the material selection stage is presented. Twenty different specifications of materials from 1st to 4th generation of pressurized water reactors have been analyzed, covering the main designs of pressurized reactors from Western Europe, Japan and Russia. Thus, the results show that steels 15Kh2MFAA, 20MnMoNi55 and SA533 Gr.B Cl.1 are the best material options to prevent the embrittlement induced by radiation&#8230; See all&#8230;<\/p>\n","protected":false},"author":7459,"featured_media":0,"comment_status":"closed","ping_status":"open","sticky":false,"template":"","format":"standard","meta":{"footnotes":""},"categories":[9],"tags":[],"class_list":{"0":"post-1193","1":"post","2":"type-post","3":"status-publish","4":"format-standard","6":"category-publicaciones"},"_links":{"self":[{"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/posts\/1193","targetHints":{"allow":["GET"]}}],"collection":[{"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/posts"}],"about":[{"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/types\/post"}],"author":[{"embeddable":true,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/users\/7459"}],"replies":[{"embeddable":true,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/comments?post=1193"}],"version-history":[{"count":5,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/posts\/1193\/revisions"}],"predecessor-version":[{"id":1203,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/posts\/1193\/revisions\/1203"}],"wp:attachment":[{"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/media?parent=1193"}],"wp:term":[{"taxonomy":"category","embeddable":true,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/categories?post=1193"},{"taxonomy":"post_tag","embeddable":true,"href":"https:\/\/blogs.uned.es\/grupo-afp\/wp-json\/wp\/v2\/tags?post=1193"}],"curies":[{"name":"wp","href":"https:\/\/api.w.org\/{rel}","templated":true}]}}