A benchtop comparison of drying methods relevant to failed spent nuclear fuel
A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of...
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| Veröffentlicht in: | Progress in nuclear energy (New series) 2019-08, Vol.115, p.120-125 |
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| container_title | Progress in nuclear energy (New series) |
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| creator | Goode, James B. Hambley, David I. Hanson, Bruce C. |
| description | A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel.
A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further.
Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate. |
| doi_str_mv | 10.1016/j.pnucene.2019.03.025 |
| format | Article |
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A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further.
Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2019.03.025</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>AGR ; Cracks ; Dry storage ; Drying ; Drying agents ; Energy consumption ; Gas cooled reactors ; Nuclear fuel ; Nuclear fuels ; Pinholes ; Reprocessing ; Spent nuclear fuels ; Stainless steel ; Stainless steels ; Stress corrosion cracking</subject><ispartof>Progress in nuclear energy (New series), 2019-08, Vol.115, p.120-125</ispartof><rights>2019 Elsevier Ltd</rights><rights>Copyright Elsevier BV Aug 2019</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c384t-393e2c7847f53760c6e1567053478bfa910ced1a6995c24586f02793f08e04a63</citedby><cites>FETCH-LOGICAL-c384t-393e2c7847f53760c6e1567053478bfa910ced1a6995c24586f02793f08e04a63</cites><orcidid>0000-0002-4900-7153</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0149197019300903$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3536,27903,27904,65309</link.rule.ids></links><search><creatorcontrib>Goode, James B.</creatorcontrib><creatorcontrib>Hambley, David I.</creatorcontrib><creatorcontrib>Hanson, Bruce C.</creatorcontrib><title>A benchtop comparison of drying methods relevant to failed spent nuclear fuel</title><title>Progress in nuclear energy (New series)</title><description>A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel.
A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further.
Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate.</description><subject>AGR</subject><subject>Cracks</subject><subject>Dry storage</subject><subject>Drying</subject><subject>Drying agents</subject><subject>Energy consumption</subject><subject>Gas cooled reactors</subject><subject>Nuclear fuel</subject><subject>Nuclear fuels</subject><subject>Pinholes</subject><subject>Reprocessing</subject><subject>Spent nuclear fuels</subject><subject>Stainless steel</subject><subject>Stainless steels</subject><subject>Stress corrosion cracking</subject><issn>0149-1970</issn><issn>1878-4224</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNqFkMtKw0AUhgdRsFYfQRhwnXjmlklWUoo3qLjR9TCdnLEpaSbOJIW-vSnt3tXhh__C-Qi5Z5AzYMXjNu-70WGHOQdW5SBy4OqCzFipy0xyLi_JDJisMlZpuCY3KW0BmGZKzcjHgq6xc5sh9NSFXW9jk0JHg6d1PDTdD93hsAl1ohFb3NtuoEOg3jYt1jT1OOlpukUbqR-xvSVX3rYJ7853Tr5fnr-Wb9nq8_V9uVhlTpRyyEQlkDtdSu2V0AW4ApkqNCghdbn2tmLgsGa2qCrluFRl4YHrSngoEaQtxJw8nHr7GH5HTIPZhjF206ThXIEqpVQwudTJ5WJIKaI3fWx2Nh4MA3MkZ7bmTM4cyRkQZiI35Z5OOZxe2DcYTXLNBAnrJqIbTB2afxr-AEXxeLM</recordid><startdate>201908</startdate><enddate>201908</enddate><creator>Goode, James B.</creator><creator>Hambley, David I.</creator><creator>Hanson, Bruce C.</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><orcidid>https://orcid.org/0000-0002-4900-7153</orcidid></search><sort><creationdate>201908</creationdate><title>A benchtop comparison of drying methods relevant to failed spent nuclear fuel</title><author>Goode, James B. ; Hambley, David I. ; Hanson, Bruce C.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c384t-393e2c7847f53760c6e1567053478bfa910ced1a6995c24586f02793f08e04a63</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>AGR</topic><topic>Cracks</topic><topic>Dry storage</topic><topic>Drying</topic><topic>Drying agents</topic><topic>Energy consumption</topic><topic>Gas cooled reactors</topic><topic>Nuclear fuel</topic><topic>Nuclear fuels</topic><topic>Pinholes</topic><topic>Reprocessing</topic><topic>Spent nuclear fuels</topic><topic>Stainless steel</topic><topic>Stainless steels</topic><topic>Stress corrosion cracking</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Goode, James B.</creatorcontrib><creatorcontrib>Hambley, David I.</creatorcontrib><creatorcontrib>Hanson, Bruce C.</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Progress in nuclear energy (New series)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Goode, James B.</au><au>Hambley, David I.</au><au>Hanson, Bruce C.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>A benchtop comparison of drying methods relevant to failed spent nuclear fuel</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2019-08</date><risdate>2019</risdate><volume>115</volume><spage>120</spage><epage>125</epage><pages>120-125</pages><issn>0149-1970</issn><eissn>1878-4224</eissn><abstract>A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel.
A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further.
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| fulltext | fulltext |
| identifier | ISSN: 0149-1970 |
| ispartof | Progress in nuclear energy (New series), 2019-08, Vol.115, p.120-125 |
| issn | 0149-1970 1878-4224 |
| language | eng |
| recordid | cdi_proquest_journals_2250584450 |
| source | Elsevier ScienceDirect Journals |
| subjects | AGR Cracks Dry storage Drying Drying agents Energy consumption Gas cooled reactors Nuclear fuel Nuclear fuels Pinholes Reprocessing Spent nuclear fuels Stainless steel Stainless steels Stress corrosion cracking |
| title | A benchtop comparison of drying methods relevant to failed spent nuclear fuel |
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