Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule
A boron carbide capsule was previously designed and tested by Pacific Northwest National Laboratory (PNNL) and Washington State University (WSU) for spectral-tailoring in mixed spectrum reactors. The presented work used this B 4 C capsule to create a fission product sample from the irradiation of hi...
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| Veröffentlicht in: | Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767 296(2):763-767, 2013-05, Vol.296 (2), p.763-767 |
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| container_title | Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767 |
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| creator | Metz, L. A. Friese, J. I. Finn, E. C. Greenwood, L. R. Kephart, R. F. Hines, C. C. King, M. D. Henry, K. M. Wall, D. E. |
| description | A boron carbide capsule was previously designed and tested by Pacific Northwest National Laboratory (PNNL) and Washington State University (WSU) for spectral-tailoring in mixed spectrum reactors. The presented work used this B
4
C capsule to create a fission product sample from the irradiation of highly enriched uranium (HEU) with a fast fission neutron spectrum. An HEU foil was irradiated inside of the capsule in WSU’s 1 MW TRIGA reactor at full power for 200 min to produce 5.8 × 10
13
fissions. After 3 days of cooling, the sample was shipped to PNNL for radiochemical separations and analysis by gamma and beta spectroscopy. Fission yields for products were calculated from the radiometric measurements and compared to measurements from thermal neutron induced fission (analyzed in parallel with the non-thermal sample at PNNL) and published evaluated fast-pooled and thermal nuclear data. Reactor dosimetry measurements were also completed to fully characterize the neutron spectrum and total fluence of the irradiation. |
| doi_str_mv | 10.1007/s10967-012-2089-z |
| format | Article |
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4
C capsule to create a fission product sample from the irradiation of highly enriched uranium (HEU) with a fast fission neutron spectrum. An HEU foil was irradiated inside of the capsule in WSU’s 1 MW TRIGA reactor at full power for 200 min to produce 5.8 × 10
13
fissions. After 3 days of cooling, the sample was shipped to PNNL for radiochemical separations and analysis by gamma and beta spectroscopy. Fission yields for products were calculated from the radiometric measurements and compared to measurements from thermal neutron induced fission (analyzed in parallel with the non-thermal sample at PNNL) and published evaluated fast-pooled and thermal nuclear data. Reactor dosimetry measurements were also completed to fully characterize the neutron spectrum and total fluence of the irradiation.</description><identifier>ISSN: 0236-5731</identifier><identifier>EISSN: 1588-2780</identifier><identifier>DOI: 10.1007/s10967-012-2089-z</identifier><language>eng</language><publisher>Dordrecht: Springer Netherlands</publisher><subject>boron carbide ; Carbides ; Chemistry ; Chemistry and Materials Science ; Diagnostic Radiology ; Enriched uranium ; Enrichment ; Fission ; fission product yields ; Hadrons ; Heavy Ions ; Inorganic Chemistry ; Irradiation ; Nuclear Chemistry ; Nuclear engineering ; Nuclear fission ; Nuclear Physics ; Nuclear power generation ; Nuclear reactor components ; Nuclear reactors ; Physical Chemistry ; radiochemical separations ; spectral tailoring</subject><ispartof>Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767, 2013-05, Vol.296 (2), p.763-767</ispartof><rights>Akadémiai Kiadó, Budapest, Hungary 2012</rights><rights>COPYRIGHT 2013 Springer</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c387t-cc52036434ebb81337365fb938f10a75b3a664c47bdb78c2a383b684ab9c0f93</citedby><cites>FETCH-LOGICAL-c387t-cc52036434ebb81337365fb938f10a75b3a664c47bdb78c2a383b684ab9c0f93</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s10967-012-2089-z$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1007/s10967-012-2089-z$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,780,784,885,27924,27925,41488,42557,51319</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/1076688$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Metz, L. A.</creatorcontrib><creatorcontrib>Friese, J. I.</creatorcontrib><creatorcontrib>Finn, E. C.</creatorcontrib><creatorcontrib>Greenwood, L. R.</creatorcontrib><creatorcontrib>Kephart, R. F.</creatorcontrib><creatorcontrib>Hines, C. C.</creatorcontrib><creatorcontrib>King, M. D.</creatorcontrib><creatorcontrib>Henry, K. M.</creatorcontrib><creatorcontrib>Wall, D. E.</creatorcontrib><creatorcontrib>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</creatorcontrib><title>Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule</title><title>Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767</title><addtitle>J Radioanal Nucl Chem</addtitle><description>A boron carbide capsule was previously designed and tested by Pacific Northwest National Laboratory (PNNL) and Washington State University (WSU) for spectral-tailoring in mixed spectrum reactors. The presented work used this B
4
C capsule to create a fission product sample from the irradiation of highly enriched uranium (HEU) with a fast fission neutron spectrum. An HEU foil was irradiated inside of the capsule in WSU’s 1 MW TRIGA reactor at full power for 200 min to produce 5.8 × 10
13
fissions. After 3 days of cooling, the sample was shipped to PNNL for radiochemical separations and analysis by gamma and beta spectroscopy. Fission yields for products were calculated from the radiometric measurements and compared to measurements from thermal neutron induced fission (analyzed in parallel with the non-thermal sample at PNNL) and published evaluated fast-pooled and thermal nuclear data. Reactor dosimetry measurements were also completed to fully characterize the neutron spectrum and total fluence of the irradiation.</description><subject>boron carbide</subject><subject>Carbides</subject><subject>Chemistry</subject><subject>Chemistry and Materials Science</subject><subject>Diagnostic Radiology</subject><subject>Enriched uranium</subject><subject>Enrichment</subject><subject>Fission</subject><subject>fission product yields</subject><subject>Hadrons</subject><subject>Heavy Ions</subject><subject>Inorganic Chemistry</subject><subject>Irradiation</subject><subject>Nuclear Chemistry</subject><subject>Nuclear engineering</subject><subject>Nuclear fission</subject><subject>Nuclear Physics</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Physical Chemistry</subject><subject>radiochemical separations</subject><subject>spectral tailoring</subject><issn>0236-5731</issn><issn>1588-2780</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2013</creationdate><recordtype>article</recordtype><recordid>eNp9UT2P1DAQtRBILAs_gM6ioslhx4ntlKcTB0gn0VxvjZ3Jrk-JvXiSYu_X41Wo0RSjGb335uMx9lmKOymE-UZSDNo0QrZNK-zQvL5hB9lb27TGirfsIFqlm94o-Z59IHoRQgzWqgODx0gUc-LXiPPIFwTaCi6YVuJTyQs_x9N5vnJMJYYzjnwrkOK28FgKjBHW2oqJ4ogcuM-lKgUo_lYHuNA240f2boKZ8NO_fGTPj9-fH342T79__Hq4f2qCsmZtQuhboXSnOvTeSqWM0v3kB2UnKcD0XoHWXeiMH72xoQVllde2Az8EMQ3qyL7sspnW6CjEFcM55JQwrE4Ko3W998i-7qBLyX82pNUtkQLOMyTMGzmpjeyGXpub3t0OPcGMLqYprwVCjRGXWHVxirV_XzcWg7B19SOTOyGUTFRwcpcSFyjXOt3dPHK7R6565G4eudfKaXcOVWw6YXEveSupvuk_pL94FZUw</recordid><startdate>20130501</startdate><enddate>20130501</enddate><creator>Metz, L. A.</creator><creator>Friese, J. I.</creator><creator>Finn, E. C.</creator><creator>Greenwood, L. R.</creator><creator>Kephart, R. F.</creator><creator>Hines, C. C.</creator><creator>King, M. D.</creator><creator>Henry, K. M.</creator><creator>Wall, D. E.</creator><general>Springer Netherlands</general><general>Springer</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7SU</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>20130501</creationdate><title>Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule</title><author>Metz, L. A. ; Friese, J. I. ; Finn, E. C. ; Greenwood, L. R. ; Kephart, R. F. ; Hines, C. C. ; King, M. D. ; Henry, K. M. ; Wall, D. E.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c387t-cc52036434ebb81337365fb938f10a75b3a664c47bdb78c2a383b684ab9c0f93</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2013</creationdate><topic>boron carbide</topic><topic>Carbides</topic><topic>Chemistry</topic><topic>Chemistry and Materials Science</topic><topic>Diagnostic Radiology</topic><topic>Enriched uranium</topic><topic>Enrichment</topic><topic>Fission</topic><topic>fission product yields</topic><topic>Hadrons</topic><topic>Heavy Ions</topic><topic>Inorganic Chemistry</topic><topic>Irradiation</topic><topic>Nuclear Chemistry</topic><topic>Nuclear engineering</topic><topic>Nuclear fission</topic><topic>Nuclear Physics</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Physical Chemistry</topic><topic>radiochemical separations</topic><topic>spectral tailoring</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Metz, L. A.</creatorcontrib><creatorcontrib>Friese, J. I.</creatorcontrib><creatorcontrib>Finn, E. C.</creatorcontrib><creatorcontrib>Greenwood, L. R.</creatorcontrib><creatorcontrib>Kephart, R. F.</creatorcontrib><creatorcontrib>Hines, C. C.</creatorcontrib><creatorcontrib>King, M. D.</creatorcontrib><creatorcontrib>Henry, K. M.</creatorcontrib><creatorcontrib>Wall, D. E.</creatorcontrib><creatorcontrib>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</creatorcontrib><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Environmental 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>OSTI.GOV</collection><jtitle>Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Metz, L. A.</au><au>Friese, J. I.</au><au>Finn, E. C.</au><au>Greenwood, L. R.</au><au>Kephart, R. F.</au><au>Hines, C. C.</au><au>King, M. D.</au><au>Henry, K. M.</au><au>Wall, D. E.</au><aucorp>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule</atitle><jtitle>Journal of Radioanalytical and Nuclear Chemistry, 296(2):763-767</jtitle><stitle>J Radioanal Nucl Chem</stitle><date>2013-05-01</date><risdate>2013</risdate><volume>296</volume><issue>2</issue><spage>763</spage><epage>767</epage><pages>763-767</pages><issn>0236-5731</issn><eissn>1588-2780</eissn><abstract>A boron carbide capsule was previously designed and tested by Pacific Northwest National Laboratory (PNNL) and Washington State University (WSU) for spectral-tailoring in mixed spectrum reactors. The presented work used this B
4
C capsule to create a fission product sample from the irradiation of highly enriched uranium (HEU) with a fast fission neutron spectrum. An HEU foil was irradiated inside of the capsule in WSU’s 1 MW TRIGA reactor at full power for 200 min to produce 5.8 × 10
13
fissions. After 3 days of cooling, the sample was shipped to PNNL for radiochemical separations and analysis by gamma and beta spectroscopy. Fission yields for products were calculated from the radiometric measurements and compared to measurements from thermal neutron induced fission (analyzed in parallel with the non-thermal sample at PNNL) and published evaluated fast-pooled and thermal nuclear data. Reactor dosimetry measurements were also completed to fully characterize the neutron spectrum and total fluence of the irradiation.</abstract><cop>Dordrecht</cop><pub>Springer Netherlands</pub><doi>10.1007/s10967-012-2089-z</doi><tpages>5</tpages></addata></record> |
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| subjects | boron carbide Carbides Chemistry Chemistry and Materials Science Diagnostic Radiology Enriched uranium Enrichment Fission fission product yields Hadrons Heavy Ions Inorganic Chemistry Irradiation Nuclear Chemistry Nuclear engineering Nuclear fission Nuclear Physics Nuclear power generation Nuclear reactor components Nuclear reactors Physical Chemistry radiochemical separations spectral tailoring |
| title | Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule |
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