<?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>2026-09-20T18:08:40Z</responseDate><request verb="GetRecord" identifier="oai:dspace.mit.edu:1721.1/82453" metadataPrefix="dim">https://dspace.mit.edu/server/oai/request</request><GetRecord><record><header><identifier>oai:dspace.mit.edu:1721.1/82453</identifier><datestamp>2022-01-13T07:54:05Z</datestamp><setSpec>com_1721.1_7582</setSpec><setSpec>com_1721.1_7581</setSpec><setSpec>col_1721.1_131023</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">Ron Ballinger.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="author" lang="en_US">Black, Bradley P. (Bradley Patrick)</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="other" lang="en_US">Massachusetts Institute of Technology. Department of Nuclear Science and Engineering.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="department">Massachusetts Institute of Technology. Department of Nuclear Science and Engineering</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="accessioned">2013-11-18T19:25:03Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="available">2013-11-18T19:25:03Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="issued" lang="en_US">2013</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="uri">http://hdl.handle.net/1721.1/82453</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="oclc" lang="en_US">863060120</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.</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 123-133).</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="abstract" lang="en_US">Used nuclear fuel dry storage canisters will likely be tasked with holding used nuclear fuel for a period longer than originally intended. Originally designed for 20 years, the storage time will likely approach 100 years. These canisters are fabricated from rolled and welded austenitic stainless steel plate. Most of the storage facilities are located on coastal or brackish water sites with environments containing moisture and chloride ions that can cause stress corrosion cracking (SCC). Residual stresses from the welding process provide the tensile stress for crack initiation and propagation which could eventually compromise canister integrity, allowing the release of radioactive material to the environment. If it is assumed that a tensile stress, predominantly from welding, is constant through the material thickness, this would suggest that failure will be initiation controlled. However, prior studies and practical experience indicate that residual stress varies as a function of depth into a welded material, and that stresses can decrease to zero or even go into compression. This would indicate that at some point, crack propagation could be slowed or even be stopped. In order to predict the time to failure of canister material by stress corrosion cracking, it is therefore necessary to know the actual residual stress distribution through the thickness of canister welds. This thesis investigates dry storage canister designs, canister welds, and contributing factors to residual stress, as well as prior studies of residual stress in welded stainless steel piping and chloride stress corrosion crack propagation rates. From this investigation, an estimate is made for the likely residual stress distribution in a typical canister weld, and the effect of residual stress on canister life prediction is examined. The analysis suggests that residual stress distribution has a tremendous impact on a canister's projected time to failure, and that residual tensile stresses in the heat-affected zone of canister welds could become low enough to result in crack arrest.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="statementofresponsibility" lang="en_US">by Bradley P. Black.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="degree" lang="en_US">S.M.</dim:field>
   <dim:field mdschema="dc" element="format" qualifier="extent" lang="en_US">160 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">M.I.T. theses are protected by 
copyright. They may be viewed from this source for any purpose, but 
reproduction or distribution in any format is prohibited without written 
permission. See provided URL for inquiries about 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">Nuclear Science and Engineering.</dim:field>
   <dim:field mdschema="dc" element="title" lang="en_US">Effect of residual stress on the life prediction of dry storage canisters for used nuclear fuel</dim:field>
   <dim:field mdschema="dc" element="type" lang="en_US">Thesis</dim:field>
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	&lt;Language>eng&lt;/Language>
   	&lt;Title>Effect of residual stress on the life prediction of dry storage canisters for used nuclear fuel&lt;/Title>
   	&lt;PublishedIn>
    	&lt;Publication>
      	&lt;/Publication>
   	&lt;/PublishedIn>
   	&lt;PublicationDate>2013&lt;/PublicationDate>
   	&lt;Authors>
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        	&lt;DisplayName>Black, Bradley P. (Bradley Patrick)&lt;/DisplayName>
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            &lt;DisplayName>Massachusetts Institute of Technology&lt;/DisplayName>
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    &lt;License>http://dspace.mit.edu/handle/1721.1/7582&lt;/License>
    &lt;Keyword>Nuclear Science and Engineering.&lt;/Keyword>
   	&lt;Abstract>Used nuclear fuel dry storage canisters will likely be tasked with holding used nuclear fuel for a period longer than originally intended. Originally designed for 20 years, the storage time will likely approach 100 years. These canisters are fabricated from rolled and welded austenitic stainless steel plate. Most of the storage facilities are located on coastal or brackish water sites with environments containing moisture and chloride ions that can cause stress corrosion cracking (SCC). Residual stresses from the welding process provide the tensile stress for crack initiation and propagation which could eventually compromise canister integrity, allowing the release of radioactive material to the environment. If it is assumed that a tensile stress, predominantly from welding, is constant through the material thickness, this would suggest that failure will be initiation controlled. However, prior studies and practical experience indicate that residual stress varies as a function of depth into a welded material, and that stresses can decrease to zero or even go into compression. This would indicate that at some point, crack propagation could be slowed or even be stopped. In order to predict the time to failure of canister material by stress corrosion cracking, it is therefore necessary to know the actual residual stress distribution through the thickness of canister welds. This thesis investigates dry storage canister designs, canister welds, and contributing factors to residual stress, as well as prior studies of residual stress in welded stainless steel piping and chloride stress corrosion crack propagation rates. From this investigation, an estimate is made for the likely residual stress distribution in a typical canister weld, and the effect of residual stress on canister life prediction is examined. The analysis suggests that residual stress distribution has a tremendous impact on a canister&amp;apos;s projected time to failure, and that residual tensile stresses in the heat-affected zone of canister welds could become low enough to result in crack arrest.&lt;/Abstract>
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