<?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>2026-09-19T17:28:13Z</responseDate><request verb="GetRecord" identifier="oai:dspace.mit.edu:1721.1/119939" metadataPrefix="dim">https://dspace.mit.edu/server/oai/request</request><GetRecord><record><header><identifier>oai:dspace.mit.edu:1721.1/119939</identifier><datestamp>2022-01-13T07:54:05Z</datestamp><setSpec>com_1721.1_7582</setSpec><setSpec>com_1721.1_7581</setSpec><setSpec>col_1721.1_131024</setSpec></header><metadata><dim:dim xmlns:dim="http://www.dspace.org/xmlns/dspace/dim" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns:doc="http://www.lyncode.com/xoai" xsi:schemaLocation="http://www.dspace.org/xmlns/dspace/dim http://www.dspace.org/schema/dim.xsd">
   <dim:field mdschema="dc" element="contributor" qualifier="advisor" lang="en_US">Zachary Hartwig.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="author" lang="en_US">Nick Schwartz, Nick (Nick Raoul)</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="other" lang="en_US">Massachusetts Institute of Technology. Department of Mechanical Engineering.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="department">Massachusetts Institute of Technology. Department of Mechanical Engineering</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="accessioned">2019-01-11T16:03:59Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="available">2019-01-11T16:03:59Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="copyright" lang="en_US">2018</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="issued" lang="en_US">2018</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="uri">http://hdl.handle.net/1721.1/119939</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="oclc" lang="en_US">1079911376</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Thesis: S.B., Massachusetts Institute of Technology, Department of Mechanical Engineering, 2018.</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Cataloged from PDF version of thesis.</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Includes bibliographical references (pages 24-25).</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="abstract" lang="en_US">Fusion energy is a promising carbon-free, limitless source of energy that could contribute to mitigating global climate change. One of the critical challenges in realizing fusion energy is the survival of structural materials in the extreme environment of a fusion device. Specifically, materials that surround the 100 million °C plasma must survive high temperatures (>500 °C), intense thermal cycling, transient high heat loads, large structural forces during off-normal plasma events, and exposure to high energy neutrons. Neutron exposure leads to high levels of radiation damage, which results in changes to critical material properties such as ductility and strength. In order to facilitate a better understanding of the effect of radiation on fusion material properties at high temperatures, a novel high-vacuum (&lt;106 torr), high-temperature (&lt;1000°C), tensile testing stand for irradiated specimens was designed and constructed. The test stand was designed to perform tensile testing of structural materials that have been irradiated by 12 MeV protons, which emulate the material response to high-energy neutrons produced in a deuterium-tritium burning fusion device. The specimen will then be heated to 500-1000 °C and tensile tested in high vacuum to eliminate sample oxidation and provide clean measurements. The design and fabrication of the test stand are given in this thesis, and first results from its commissioning are presented.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="statementofresponsibility" lang="en_US">by Nick Schwartz.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="degree" lang="en_US">S.B.</dim:field>
   <dim:field mdschema="dc" element="format" qualifier="extent" lang="en_US">25 pages</dim:field>
   <dim:field mdschema="dc" element="language" qualifier="iso" lang="en_US">eng</dim:field>
   <dim:field mdschema="dc" element="publisher" lang="en_US">Massachusetts Institute of Technology</dim:field>
   <dim:field mdschema="dc" element="rights" lang="en_US">MIT theses are protected by copyright. They may be viewed, downloaded, or printed from this source but further reproduction or distribution in any format is prohibited without written permission.</dim:field>
   <dim:field mdschema="dc" element="rights" qualifier="uri" lang="en_US">http://dspace.mit.edu/handle/1721.1/7582</dim:field>
   <dim:field mdschema="dc" element="subject" lang="en_US">Mechanical Engineering.</dim:field>
   <dim:field mdschema="dc" element="title" lang="en_US">Design and construction of high-temperature, high-vacuum tensile tester for fusion reactor materials</dim:field>
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   	&lt;Title>Design and construction of high-temperature, high-vacuum tensile tester for fusion reactor materials&lt;/Title>
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   	&lt;PublicationDate>2018&lt;/PublicationDate>
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        	&lt;DisplayName>Nick Schwartz, Nick (Nick Raoul)&lt;/DisplayName>
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    &lt;Keyword>Mechanical Engineering.&lt;/Keyword>
   	&lt;Abstract>Fusion energy is a promising carbon-free, limitless source of energy that could contribute to mitigating global climate change. One of the critical challenges in realizing fusion energy is the survival of structural materials in the extreme environment of a fusion device. Specifically, materials that surround the 100 million °C plasma must survive high temperatures (&amp;gt;500 °C), intense thermal cycling, transient high heat loads, large structural forces during off-normal plasma events, and exposure to high energy neutrons. Neutron exposure leads to high levels of radiation damage, which results in changes to critical material properties such as ductility and strength. In order to facilitate a better understanding of the effect of radiation on fusion material properties at high temperatures, a novel high-vacuum (&amp;lt;106 torr), high-temperature (&amp;lt;1000°C), tensile testing stand for irradiated specimens was designed and constructed. The test stand was designed to perform tensile testing of structural materials that have been irradiated by 12 MeV protons, which emulate the material response to high-energy neutrons produced in a deuterium-tritium burning fusion device. The specimen will then be heated to 500-1000 °C and tensile tested in high vacuum to eliminate sample oxidation and provide clean measurements. The design and fabrication of the test stand are given in this thesis, and first results from its commissioning are presented.&lt;/Abstract>
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