Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility
•Additively manufactured (AM) steel was found to be less susceptible to irradiation assisted stress corrosion cracking (IASCC) than wrought material•Irradiation induced voids in the AM steel were larger though less numerous than the voids in the wrought material•Overall swelling in AM steel was less...
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description | •Additively manufactured (AM) steel was found to be less susceptible to irradiation assisted stress corrosion cracking (IASCC) than wrought material•Irradiation induced voids in the AM steel were larger though less numerous than the voids in the wrought material•Overall swelling in AM steel was less than that of wrought steel•Localized deformation was more severe in the AM steel than the wrought steel
While additive manufacturing (AM) is an area of increasing interest to the nuclear industry, there are significant research and development needs prior to successful implementation of additively manufactured components into reactors. AM steel behaves differently than traditional wrought material, as has been observed in numerous mechanical testing studies. The nuclear industry must also understand the material response to irradiation. This work examines the irradiation damage and the irradiation assisted stress corrosion cracking behavior (IASCC) of both proton irradiated AM and wrought 316L steel. For IASCC testing, specimens were strained to 4% plastic strain in a simulated boiling water reactor environment (288°C, 0.2 µS/cm). Transmission and scanning electron microscopy, confocal microscopy, and X-ray computed tomography were used to examine coupons of the material as well as tensile bars used in the IASCC testing. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, some IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. Electron microscopy has shown significantly fewer radiation induced voids formed in the AM steel. While the pre-existing pore network in the AM steel may act as a sink to point defects, this is not expected to be the major factor in the reduced swelling observed in the AM steel. The lower density of radiation induced voids was expected to contribute to the IASCC resistance by decreasing the localization of deformation in the irradiated specimens, however, severity of localized deformation in AM steel, measured in dislocation channel spacing and height, was similar or more severe to that found in wrought. The presence of severe cracking in the wrought specimens did not allow for a direct comparison of localized deformation severities between the AM and wrought steel. |
doi_str_mv | 10.1016/j.jnucmat.2020.152739 |
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While additive manufacturing (AM) is an area of increasing interest to the nuclear industry, there are significant research and development needs prior to successful implementation of additively manufactured components into reactors. AM steel behaves differently than traditional wrought material, as has been observed in numerous mechanical testing studies. The nuclear industry must also understand the material response to irradiation. This work examines the irradiation damage and the irradiation assisted stress corrosion cracking behavior (IASCC) of both proton irradiated AM and wrought 316L steel. For IASCC testing, specimens were strained to 4% plastic strain in a simulated boiling water reactor environment (288°C, 0.2 µS/cm). Transmission and scanning electron microscopy, confocal microscopy, and X-ray computed tomography were used to examine coupons of the material as well as tensile bars used in the IASCC testing. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, some IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. Electron microscopy has shown significantly fewer radiation induced voids formed in the AM steel. While the pre-existing pore network in the AM steel may act as a sink to point defects, this is not expected to be the major factor in the reduced swelling observed in the AM steel. The lower density of radiation induced voids was expected to contribute to the IASCC resistance by decreasing the localization of deformation in the irradiated specimens, however, severity of localized deformation in AM steel, measured in dislocation channel spacing and height, was similar or more severe to that found in wrought. The presence of severe cracking in the wrought specimens did not allow for a direct comparison of localized deformation severities between the AM and wrought steel.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2020.152739</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Additive manufacturing ; Austenitic stainless steels ; Boiling water reactors ; Computed tomography ; Confocal microscopy ; Corrosion ; Deformation ; Electron microscopy ; Irradiation ; Localization ; Mechanical properties ; Mechanical tests ; Microscopy ; Nuclear reactor components ; Nuclear reactors ; Plastic deformation ; Point defects ; Proton irradiation ; R&D ; Radiation ; Radiation damage ; Radiation effects ; Reactors ; Research & development ; Scanning electron microscopy ; Steel ; Stress corrosion ; Stress corrosion cracking</subject><ispartof>Journal of nuclear materials, 2021-03, Vol.545 (C), p.152739, Article 152739</ispartof><rights>2020</rights><rights>Copyright Elsevier BV Mar 2021</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c411t-947e3dc4f45e0b538c04a692b52d1af78da8e5f66eb082f7b67fde7dc6440f863</citedby><cites>FETCH-LOGICAL-c411t-947e3dc4f45e0b538c04a692b52d1af78da8e5f66eb082f7b67fde7dc6440f863</cites><orcidid>0000-0003-2887-639X ; 0000-0002-7835-2888 ; 0000-0002-4835-5041 ; 0000000278352888 ; 0000000248355041 ; 000000032887639X</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.jnucmat.2020.152739$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,780,784,885,3550,27924,27925,45995</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/1810970$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>McMurtrey, M.</creatorcontrib><creatorcontrib>Sun, C.</creatorcontrib><creatorcontrib>Rupp, R.E.</creatorcontrib><creatorcontrib>Shiau, C.-H.</creatorcontrib><creatorcontrib>Hanbury, R.</creatorcontrib><creatorcontrib>Jerred, N.</creatorcontrib><creatorcontrib>O'Brien, R.</creatorcontrib><title>Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility</title><title>Journal of nuclear materials</title><description>•Additively manufactured (AM) steel was found to be less susceptible to irradiation assisted stress corrosion cracking (IASCC) than wrought material•Irradiation induced voids in the AM steel were larger though less numerous than the voids in the wrought material•Overall swelling in AM steel was less than that of wrought steel•Localized deformation was more severe in the AM steel than the wrought steel
While additive manufacturing (AM) is an area of increasing interest to the nuclear industry, there are significant research and development needs prior to successful implementation of additively manufactured components into reactors. AM steel behaves differently than traditional wrought material, as has been observed in numerous mechanical testing studies. The nuclear industry must also understand the material response to irradiation. This work examines the irradiation damage and the irradiation assisted stress corrosion cracking behavior (IASCC) of both proton irradiated AM and wrought 316L steel. For IASCC testing, specimens were strained to 4% plastic strain in a simulated boiling water reactor environment (288°C, 0.2 µS/cm). Transmission and scanning electron microscopy, confocal microscopy, and X-ray computed tomography were used to examine coupons of the material as well as tensile bars used in the IASCC testing. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, some IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. Electron microscopy has shown significantly fewer radiation induced voids formed in the AM steel. While the pre-existing pore network in the AM steel may act as a sink to point defects, this is not expected to be the major factor in the reduced swelling observed in the AM steel. The lower density of radiation induced voids was expected to contribute to the IASCC resistance by decreasing the localization of deformation in the irradiated specimens, however, severity of localized deformation in AM steel, measured in dislocation channel spacing and height, was similar or more severe to that found in wrought. The presence of severe cracking in the wrought specimens did not allow for a direct comparison of localized deformation severities between the AM and wrought steel.</description><subject>Additive manufacturing</subject><subject>Austenitic stainless steels</subject><subject>Boiling water reactors</subject><subject>Computed tomography</subject><subject>Confocal microscopy</subject><subject>Corrosion</subject><subject>Deformation</subject><subject>Electron microscopy</subject><subject>Irradiation</subject><subject>Localization</subject><subject>Mechanical properties</subject><subject>Mechanical tests</subject><subject>Microscopy</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Plastic deformation</subject><subject>Point defects</subject><subject>Proton irradiation</subject><subject>R&D</subject><subject>Radiation</subject><subject>Radiation damage</subject><subject>Radiation effects</subject><subject>Reactors</subject><subject>Research & development</subject><subject>Scanning electron microscopy</subject><subject>Steel</subject><subject>Stress corrosion</subject><subject>Stress corrosion cracking</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNqFkc1u3CAUhVHVSp0mfYRKqF17AtiAvaqqqD-RRsomWSMMlwTXA1PAI83z9EWL5Sy6ywrp8p2je-5B6BMle0qouJn2U1jMUZc9I6zOOJPt8AbtaC_bpusZeYt2hDDWtJTy9-hDzhMhhA-E79Dfu3CGXPyTLj4GHB0uz4B9Str6bQTOgSkZ-4C1tb74M8wXfNRhcdqUJYHFLRUHnAvAjBPkZS4-PK28BZNA50r8b6hz9hW2VVHpjE1MKeb1xyRtfq_avGQDp-JHP_tyuUbvnJ4zfHx5r9Djj-8Pt7-aw_3Pu9tvh8Z0lJZm6CS01nSu40BG3vaGdFoMbOTMUu1kb3UP3AkBI-mZk6OQzoK0RnQdcb1or9DnzTfWg6hsfAHzbGIINb-iPSWDJBX6skGnFP8s9XRqiksKdS_Ful5SIUVLK8U3ytRoOYFTp-SPOl0UJWotTU3qpTS1lqa20qru66aDmvPsIa1rQDBgfVq3sNG_4vAP3qOncw</recordid><startdate>202103</startdate><enddate>202103</enddate><creator>McMurtrey, M.</creator><creator>Sun, C.</creator><creator>Rupp, R.E.</creator><creator>Shiau, C.-H.</creator><creator>Hanbury, R.</creator><creator>Jerred, N.</creator><creator>O'Brien, R.</creator><general>Elsevier B.V</general><general>Elsevier BV</general><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SR</scope><scope>7ST</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>SOI</scope><scope>OTOTI</scope><orcidid>https://orcid.org/0000-0003-2887-639X</orcidid><orcidid>https://orcid.org/0000-0002-7835-2888</orcidid><orcidid>https://orcid.org/0000-0002-4835-5041</orcidid><orcidid>https://orcid.org/0000000278352888</orcidid><orcidid>https://orcid.org/0000000248355041</orcidid><orcidid>https://orcid.org/000000032887639X</orcidid></search><sort><creationdate>202103</creationdate><title>Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility</title><author>McMurtrey, M. ; Sun, C. ; Rupp, R.E. ; Shiau, C.-H. ; Hanbury, R. ; Jerred, N. ; O'Brien, R.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c411t-947e3dc4f45e0b538c04a692b52d1af78da8e5f66eb082f7b67fde7dc6440f863</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Additive manufacturing</topic><topic>Austenitic stainless steels</topic><topic>Boiling water reactors</topic><topic>Computed tomography</topic><topic>Confocal microscopy</topic><topic>Corrosion</topic><topic>Deformation</topic><topic>Electron microscopy</topic><topic>Irradiation</topic><topic>Localization</topic><topic>Mechanical properties</topic><topic>Mechanical tests</topic><topic>Microscopy</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Plastic deformation</topic><topic>Point defects</topic><topic>Proton irradiation</topic><topic>R&D</topic><topic>Radiation</topic><topic>Radiation damage</topic><topic>Radiation effects</topic><topic>Reactors</topic><topic>Research & development</topic><topic>Scanning electron microscopy</topic><topic>Steel</topic><topic>Stress corrosion</topic><topic>Stress corrosion cracking</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>McMurtrey, M.</creatorcontrib><creatorcontrib>Sun, C.</creatorcontrib><creatorcontrib>Rupp, R.E.</creatorcontrib><creatorcontrib>Shiau, C.-H.</creatorcontrib><creatorcontrib>Hanbury, R.</creatorcontrib><creatorcontrib>Jerred, N.</creatorcontrib><creatorcontrib>O'Brien, R.</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>McMurtrey, M.</au><au>Sun, C.</au><au>Rupp, R.E.</au><au>Shiau, C.-H.</au><au>Hanbury, R.</au><au>Jerred, N.</au><au>O'Brien, R.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility</atitle><jtitle>Journal of nuclear materials</jtitle><date>2021-03</date><risdate>2021</risdate><volume>545</volume><issue>C</issue><spage>152739</spage><pages>152739-</pages><artnum>152739</artnum><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>•Additively manufactured (AM) steel was found to be less susceptible to irradiation assisted stress corrosion cracking (IASCC) than wrought material•Irradiation induced voids in the AM steel were larger though less numerous than the voids in the wrought material•Overall swelling in AM steel was less than that of wrought steel•Localized deformation was more severe in the AM steel than the wrought steel
While additive manufacturing (AM) is an area of increasing interest to the nuclear industry, there are significant research and development needs prior to successful implementation of additively manufactured components into reactors. AM steel behaves differently than traditional wrought material, as has been observed in numerous mechanical testing studies. The nuclear industry must also understand the material response to irradiation. This work examines the irradiation damage and the irradiation assisted stress corrosion cracking behavior (IASCC) of both proton irradiated AM and wrought 316L steel. For IASCC testing, specimens were strained to 4% plastic strain in a simulated boiling water reactor environment (288°C, 0.2 µS/cm). Transmission and scanning electron microscopy, confocal microscopy, and X-ray computed tomography were used to examine coupons of the material as well as tensile bars used in the IASCC testing. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, some IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. Electron microscopy has shown significantly fewer radiation induced voids formed in the AM steel. While the pre-existing pore network in the AM steel may act as a sink to point defects, this is not expected to be the major factor in the reduced swelling observed in the AM steel. The lower density of radiation induced voids was expected to contribute to the IASCC resistance by decreasing the localization of deformation in the irradiated specimens, however, severity of localized deformation in AM steel, measured in dislocation channel spacing and height, was similar or more severe to that found in wrought. The presence of severe cracking in the wrought specimens did not allow for a direct comparison of localized deformation severities between the AM and wrought steel.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2020.152739</doi><orcidid>https://orcid.org/0000-0003-2887-639X</orcidid><orcidid>https://orcid.org/0000-0002-7835-2888</orcidid><orcidid>https://orcid.org/0000-0002-4835-5041</orcidid><orcidid>https://orcid.org/0000000278352888</orcidid><orcidid>https://orcid.org/0000000248355041</orcidid><orcidid>https://orcid.org/000000032887639X</orcidid><oa>free_for_read</oa></addata></record> |
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source | ScienceDirect Journals (5 years ago - present) |
subjects | Additive manufacturing Austenitic stainless steels Boiling water reactors Computed tomography Confocal microscopy Corrosion Deformation Electron microscopy Irradiation Localization Mechanical properties Mechanical tests Microscopy Nuclear reactor components Nuclear reactors Plastic deformation Point defects Proton irradiation R&D Radiation Radiation damage Radiation effects Reactors Research & development Scanning electron microscopy Steel Stress corrosion Stress corrosion cracking |
title | Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility |
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