Radiation damage effects in candidate titanates for Pu disposition: Zirconolite
Results from studies of radiation-induced damage from the alpha decay of 238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density d...
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| Veröffentlicht in: | Journal of nuclear materials 2008-01, Vol.372 (1), p.16-31 |
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| container_title | Journal of nuclear materials |
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| creator | Strachan, D.M. Scheele, R.D. Buck, E.C. Kozelisky, A.E. Sell, R.L. Elovich, R.J. Buchmiller, W.C. |
| description | Results from studies of radiation-induced damage from the alpha decay of
238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6
×
10
18
α/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)
×
10
−3
g/(m
2
d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu. |
| doi_str_mv | 10.1016/j.jnucmat.2007.01.278 |
| format | Article |
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238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6
×
10
18
α/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)
×
10
−3
g/(m
2
d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2007.01.278</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; GENERAL STUDIES OF NUCLEAR REACTORS ; Installations for energy generation and conversion: thermal and electrical energy ; leaching ; Nuclear fuels ; plutonium disposition ; radiation damage ; titanate ; waste form ; zirconolite</subject><ispartof>Journal of nuclear materials, 2008-01, Vol.372 (1), p.16-31</ispartof><rights>2007 Elsevier B.V.</rights><rights>2008 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c396t-b18393db1096fe8356155388d02641915c2bb9cb7c681447f130627f3efa0d63</citedby><cites>FETCH-LOGICAL-c396t-b18393db1096fe8356155388d02641915c2bb9cb7c681447f130627f3efa0d63</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311507003170$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,776,780,881,3537,27901,27902,65534</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=20028865$$DView record in Pascal Francis$$Hfree_for_read</backlink><backlink>$$Uhttps://www.osti.gov/biblio/927286$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Strachan, D.M.</creatorcontrib><creatorcontrib>Scheele, R.D.</creatorcontrib><creatorcontrib>Buck, E.C.</creatorcontrib><creatorcontrib>Kozelisky, A.E.</creatorcontrib><creatorcontrib>Sell, R.L.</creatorcontrib><creatorcontrib>Elovich, R.J.</creatorcontrib><creatorcontrib>Buchmiller, W.C.</creatorcontrib><creatorcontrib>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</creatorcontrib><title>Radiation damage effects in candidate titanates for Pu disposition: Zirconolite</title><title>Journal of nuclear materials</title><description>Results from studies of radiation-induced damage from the alpha decay of
238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6
×
10
18
α/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)
×
10
−3
g/(m
2
d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>GENERAL STUDIES OF NUCLEAR REACTORS</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>leaching</subject><subject>Nuclear fuels</subject><subject>plutonium disposition</subject><subject>radiation damage</subject><subject>titanate</subject><subject>waste form</subject><subject>zirconolite</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2008</creationdate><recordtype>article</recordtype><recordid>eNqFkM9rHCEYhiW0kG2aPyFgD8ltpp-6Ok4uJYS0CQRSSk69iOOP1GVWt-oG8t_HYZdee9LD837vy4PQBYGeABFfN_0m7s1W154CDD2Qng7yBK2IHFi3lhQ-oBUApR0jhJ-iT6VsAICPwFfo6Ze2QdeQIrZ6q18cdt47UwsOERsdbbC6OlxD1bF9CvYp4597bEPZpRKW4DX-HbJJMc2hus_oo9dzcefH9ww9f797vr3vHp9-PNzePHaGjaJ2E5FsZHYiMArvJOOCcM6ktEDFmoyEGzpNo5kGIyRZrwdPGAg6eOa8BivYGfpyOJtKDaqY1mz-tA2xTVcjHahcmKsDs8vp796VqrahGDfPOrq0L4o1P80BbyA_gCanUrLzapfDVuc3RUAthtVGHQ2rxbACoprhlrs8Fuhi9OyzjiaUf-GGUinFcv_bgXNNyGtweRnsonE25GWvTeE_Te_naJNk</recordid><startdate>20080115</startdate><enddate>20080115</enddate><creator>Strachan, D.M.</creator><creator>Scheele, R.D.</creator><creator>Buck, E.C.</creator><creator>Kozelisky, A.E.</creator><creator>Sell, R.L.</creator><creator>Elovich, R.J.</creator><creator>Buchmiller, W.C.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>20080115</creationdate><title>Radiation damage effects in candidate titanates for Pu disposition: Zirconolite</title><author>Strachan, D.M. ; Scheele, R.D. ; Buck, E.C. ; Kozelisky, A.E. ; Sell, R.L. ; Elovich, R.J. ; Buchmiller, W.C.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c396t-b18393db1096fe8356155388d02641915c2bb9cb7c681447f130627f3efa0d63</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2008</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>GENERAL STUDIES OF NUCLEAR REACTORS</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>leaching</topic><topic>Nuclear fuels</topic><topic>plutonium disposition</topic><topic>radiation damage</topic><topic>titanate</topic><topic>waste form</topic><topic>zirconolite</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Strachan, D.M.</creatorcontrib><creatorcontrib>Scheele, R.D.</creatorcontrib><creatorcontrib>Buck, E.C.</creatorcontrib><creatorcontrib>Kozelisky, A.E.</creatorcontrib><creatorcontrib>Sell, R.L.</creatorcontrib><creatorcontrib>Elovich, R.J.</creatorcontrib><creatorcontrib>Buchmiller, W.C.</creatorcontrib><creatorcontrib>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Strachan, D.M.</au><au>Scheele, R.D.</au><au>Buck, E.C.</au><au>Kozelisky, A.E.</au><au>Sell, R.L.</au><au>Elovich, R.J.</au><au>Buchmiller, W.C.</au><aucorp>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Radiation damage effects in candidate titanates for Pu disposition: Zirconolite</atitle><jtitle>Journal of nuclear materials</jtitle><date>2008-01-15</date><risdate>2008</risdate><volume>372</volume><issue>1</issue><spage>16</spage><epage>31</epage><pages>16-31</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>Results from studies of radiation-induced damage from the alpha decay of
238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6
×
10
18
α/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)
×
10
−3
g/(m
2
d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2007.01.278</doi><tpages>16</tpages></addata></record> |
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| ispartof | Journal of nuclear materials, 2008-01, Vol.372 (1), p.16-31 |
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| source | Elsevier ScienceDirect Journals Complete |
| subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels GENERAL STUDIES OF NUCLEAR REACTORS Installations for energy generation and conversion: thermal and electrical energy leaching Nuclear fuels plutonium disposition radiation damage titanate waste form zirconolite |
| title | Radiation damage effects in candidate titanates for Pu disposition: Zirconolite |
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