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        <identifier>oai:www.ideals.illinois.edu:2142/96429</identifier>
        <datestamp>2023-07-11</datestamp>
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          <dc:creator>Lee, Daniel K.</dc:creator>
          <dc:date>2017-07-06T18:55:04Z</dc:date>
          <dc:date>2017-07-06T18:55:04Z</dc:date>
          <dc:date>10000-01-01</dc:date>
          <dc:date>1983</dc:date>
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  Previous issue date: 1983</dc:description>
          <dc:description>Embargo set by: Seth Robbins for item 99575
Lift date: Forever
Reason: Restricted to UIUC community</dc:description>
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          <dc:identifier>http://hdl.handle.net/2142/96429</dc:identifier>
          <dc:language>en</dc:language>
          <dc:rights>Copyright 1997 Erik Stefan Kirstein</dc:rights>
          <dc:subject>nuclear engineering</dc:subject>
          <dc:subject>high temperature corrosion</dc:subject>
          <dc:subject>metallic materials</dc:subject>
          <dc:subject>nuclear reactor helium environment</dc:subject>
          <dc:subject>high temperature gas cooled reactors</dc:subject>
          <dc:subject>HTGR</dc:subject>
          <dc:subject>oxidation</dc:subject>
          <dc:subject>carburization</dc:subject>
          <dc:subject>alloy 800H</dc:subject>
          <dc:subject>hastelloy X</dc:subject>
          <dc:subject>type 310 stainless steel</dc:subject>
          <dc:subject>ductility</dc:subject>
          <dc:title>High Temperature Corrosion Studies of Metallic Materials in High Temperature Gas-Cooled Nuclear Reactor Helium Environment</dc:title>
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          <dc:type>text</dc:type>
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            <discipline>Nuclear, Plasma, and Radiological Engineering</discipline>
            <level>Thesis</level>
            <name>M.S. (master's)</name>
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