Migration and release behavior of tritium in SS316 at ambient temperature
BIXS measurements indicate that immersion into water or chemical etching of SS316 contaminated with tritium at moderate temperatures causes an immediate reduction of the outermost surface concentration of tritium. The fraction of surface tritium removed by water, i.e. 30–50%, is small in comparison...
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| Veröffentlicht in: | Journal of nuclear materials 2007-06, Vol.363-365, p.462-466 |
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| container_title | Journal of nuclear materials |
| container_volume | 363-365 |
| creator | Torikai, Y. Murata, D. Penzhorn, R.-D. Akaishi, K. Watanabe, K. Matsuyama, M. |
| description | BIXS measurements indicate that immersion into water or chemical etching of SS316 contaminated with tritium at moderate temperatures causes an immediate reduction of the outermost surface concentration of tritium. The fraction of surface tritium removed by water, i.e. 30–50%, is small in comparison to the total tritium present in the specimen. Allowing a specimen to age whose surface and subsurface had been removed by etching up to a depth where the concentration of tritium is mostly constant revealed that within a few months a re-growth of tritium up to a saturation value higher than half of that originally present on the specimen takes place. Concurrently, a small but steady liberation of tritium at rates increasing from 0.1 to 0.3kBq/h was noticed. |
| doi_str_mv | 10.1016/j.jnucmat.2007.01.043 |
| format | Article |
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Production and utilization</subject><subject>Applied sciences</subject><subject>Energy</subject><subject>Exact sciences and technology</subject><subject>Fuels</subject><subject>Hydrogen</subject><subject>Stainless steel</subject><subject>Tritium removal</subject><subject>Tritium retention</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2007</creationdate><recordtype>article</recordtype><recordid>eNqNkUtr3TAQRkVpobdpfkJAm3Znd_S0vCoh9BFI6SLJWozlcauLHzeSHMi_j8O90GW6ms355mPmMHYhoBYg7Jd9vZ_XMGGpJUBTg6hBqzdsJ1yjKu0kvGU7ACkrJYR5zz7kvAcA04LZsetf8U_CEpeZ49zzRCNhJt7RX3yMS-LLwEuKJa4TjzO_vVXCciwcpy7SXHih6UBbfk30kb0bcMx0fppn7P77t7urn9XN7x_XV5c3VdBKlgq1cg0Y1G0nTI_d0AuL0BsplbWNlojGuYZc21jQ0FqyHaK0aORgHWCnztjn495DWh5WysVPMQcaR5xpWbOXbeuc3k7_H1BKoV4HQRqjhd5AcwRDWnJONPhDihOmJy_Av6jwe39S4V9UeBB-U7HlPp0KMAcch4RziPlf2LUglDMb9_XI0fa_x0jJ57C9OVAfE4Xi-yW-0vQMTMagAQ</recordid><startdate>20070615</startdate><enddate>20070615</enddate><creator>Torikai, Y.</creator><creator>Murata, D.</creator><creator>Penzhorn, R.-D.</creator><creator>Akaishi, K.</creator><creator>Watanabe, K.</creator><creator>Matsuyama, M.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7SR</scope><scope>8BQ</scope><scope>8FD</scope><scope>JG9</scope><scope>7TB</scope><scope>7U5</scope><scope>FR3</scope><scope>L7M</scope></search><sort><creationdate>20070615</creationdate><title>Migration and release behavior of tritium in SS316 at ambient temperature</title><author>Torikai, Y. ; Murata, D. ; Penzhorn, R.-D. ; Akaishi, K. ; Watanabe, K. ; Matsuyama, M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c432t-a438705a49b15dabfd16a0d522366742aa5887e897604096e6baa26a52f680ab3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2007</creationdate><topic>Alternative fuels. 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| ispartof | Journal of nuclear materials, 2007-06, Vol.363-365, p.462-466 |
| issn | 0022-3115 1873-4820 |
| language | eng |
| recordid | cdi_proquest_miscellaneous_29988487 |
| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Alternative fuels. Production and utilization Applied sciences Energy Exact sciences and technology Fuels Hydrogen Stainless steel Tritium removal Tritium retention |
| title | Migration and release behavior of tritium in SS316 at ambient temperature |
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