<?xml version="1.0" encoding="UTF-8"?><?xml-stylesheet type="text/xsl" href="static/style.xsl"?><OAI-PMH xmlns="http://www.openarchives.org/OAI/2.0/" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xsi:schemaLocation="http://www.openarchives.org/OAI/2.0/ http://www.openarchives.org/OAI/2.0/OAI-PMH.xsd"><responseDate>2026-04-17T12:13:39Z</responseDate><request verb="GetRecord" identifier="oai:www.recercat.cat:2099.1/16357" metadataPrefix="oai_dc">https://recercat.cat/oai/request</request><GetRecord><record><header><identifier>oai:recercat.cat:2099.1/16357</identifier><datestamp>2025-07-22T15:26:18Z</datestamp><setSpec>com_2072_1033</setSpec><setSpec>col_2072_452951</setSpec></header><metadata><oai_dc:dc xmlns:oai_dc="http://www.openarchives.org/OAI/2.0/oai_dc/" xmlns:dc="http://purl.org/dc/elements/1.1/" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns:doc="http://www.lyncode.com/xoai" xsi:schemaLocation="http://www.openarchives.org/OAI/2.0/oai_dc/ http://www.openarchives.org/OAI/2.0/oai_dc.xsd">
   <dc:title>Study of stress corrosion cracking resistance of ultrafinegrained zirconium alloys</dc:title>
   <dc:creator>Nogués Martín, Pere</dc:creator>
   <dc:contributor>Nikulin, S.A.</dc:contributor>
   <dc:subject>Àrees temàtiques de la UPC::Enginyeria dels materials::Assaig de materials::Assaig de fractura</dc:subject>
   <dc:subject>Àrees temàtiques de la UPC::Enginyeria dels materials::Assaig de materials::Assaigs de corrosió</dc:subject>
   <dc:subject>Àrees temàtiques de la UPC::Enginyeria dels materials::Metal·lúrgia</dc:subject>
   <dc:subject>Zirconium alloys -- Microstructure</dc:subject>
   <dc:subject>Zirconium alloys – Corrosion</dc:subject>
   <dc:subject>Zirconium alloys – Cracking and Fracture</dc:subject>
   <dc:subject>Zirconi – Aliatges -- Microestructura</dc:subject>
   <dc:subject>Zirconi – Aliatges -- Corrosió</dc:subject>
   <dc:subject>Zirconi – Aliatges -- Fissuració i Fractura</dc:subject>
   <dc:description>A method (approach) have been developed for SCC tests of sheet specimens from zirconium alloys which includes: exposure in iodine-methanol solution, quantitative analysis of corrosion defects, tensile tests of corroded specimens and quantitative analysis of fracture surfaces and cross sections. A comparison was made between sheets of as-received and ultrafinegrained zirconium alloys for nuclear reactors to discuss its applicability in the nuclear industry.</dc:description>
   <dc:description>Outgoing</dc:description>
   <dc:date>2011</dc:date>
   <dc:type>Master thesis (pre-Bologna period)</dc:type>
   <dc:identifier>https://hdl.handle.net/2099.1/16357</dc:identifier>
   <dc:language>eng</dc:language>
   <dc:rights>Restricted access - author's decision</dc:rights>
   <dc:format>application/pdf</dc:format>
   <dc:publisher>Universitat Politècnica de Catalunya</dc:publisher>
   <dc:publisher>National University of Science and Technology MISIS</dc:publisher>
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