Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten
Retention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa with sample temperatures between 300K and 1200K. At a D plasma ion fluence of 1024/m2 on samples damaged to 0.2dpa at 300K, the retained D retention inventory is 4.6 ×1020D/m2, about ∼5.5 times higher th...
| Main Authors: | , , , , , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2017-08-01
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| Series: | Nuclear Materials and Energy |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179116301053 |
| _version_ | 1819040698215694336 |
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| author | G.R. Tynan R.P. Doerner J. Barton R. Chen S. Cui M. Simmonds Y. Wang J.S. Weaver N. Mara S. Pathak |
| author_facet | G.R. Tynan R.P. Doerner J. Barton R. Chen S. Cui M. Simmonds Y. Wang J.S. Weaver N. Mara S. Pathak |
| author_sort | G.R. Tynan |
| collection | DOAJ |
| description | Retention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa with sample temperatures between 300K and 1200K. At a D plasma ion fluence of 1024/m2 on samples damaged to 0.2dpa at 300K, the retained D retention inventory is 4.6 ×1020D/m2, about ∼5.5 times higher than in undamaged samples. The retained inventory drops to 9 ×1019D/m2 for samples damaged to 0.2dpa at 1000K, consistent with onset of vacancy annealing at a rate sufficient to overcome the elevated rate of ion beam damage; at a damage temperature of 1200K retention is nearly equal to values seen in undamaged materials. A nano-scale technique provides thermal conductivity measurements from the Cu-ion beam displacement damaged region. We find the thermal conductivity of W damaged to 0.2dpa at room temperature drops from the un-irradiated value of 182 ± 3.3W/mK to 53 ± 8W/mK. |
| first_indexed | 2024-12-21T09:13:14Z |
| format | Article |
| id | doaj.art-b4a87f8b0e8f4b658ac4a1d6879581a8 |
| institution | Directory Open Access Journal |
| issn | 2352-1791 |
| language | English |
| last_indexed | 2024-12-21T09:13:14Z |
| publishDate | 2017-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Materials and Energy |
| spelling | doaj.art-b4a87f8b0e8f4b658ac4a1d6879581a82022-12-21T19:09:12ZengElsevierNuclear Materials and Energy2352-17912017-08-0112164168Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungstenG.R. Tynan0R.P. Doerner1J. Barton2R. Chen3S. Cui4M. Simmonds5Y. Wang6J.S. Weaver7N. Mara8S. Pathak9Center for Energy Research, San Diego, La Jolla CA USA; Department of Mechanical and Aerospace Engineering, Jacobs School of Engineering, UC San Diego, La Jolla CA USA; Corresponding author at: 460 EBU II MC 0417, UC San Diego, 9500 Gilman Drive, La Jolla CA 92093.Center for Energy Research, San Diego, La Jolla CA USACenter for Energy Research, San Diego, La Jolla CA USA; Department of Mechanical and Aerospace Engineering, Jacobs School of Engineering, UC San Diego, La Jolla CA USACenter for Energy Research, San Diego, La Jolla CA USA; Department of Mechanical and Aerospace Engineering, Jacobs School of Engineering, UC San Diego, La Jolla CA USADepartment of Mechanical and Aerospace Engineering, Jacobs School of Engineering, UC San Diego, La Jolla CA USACenter for Energy Research, San Diego, La Jolla CA USA; Department of Physics, UC San Diego, La Jolla CA USAIon Beam Materials Laboratory, Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos NM USAIon Beam Materials Laboratory, Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos NM USAIon Beam Materials Laboratory, Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos NM USAIon Beam Materials Laboratory, Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos NM USARetention of plasma-implanted D is studied in W targets damaged by a Cu ion beam at up to 0.2dpa with sample temperatures between 300K and 1200K. At a D plasma ion fluence of 1024/m2 on samples damaged to 0.2dpa at 300K, the retained D retention inventory is 4.6 ×1020D/m2, about ∼5.5 times higher than in undamaged samples. The retained inventory drops to 9 ×1019D/m2 for samples damaged to 0.2dpa at 1000K, consistent with onset of vacancy annealing at a rate sufficient to overcome the elevated rate of ion beam damage; at a damage temperature of 1200K retention is nearly equal to values seen in undamaged materials. A nano-scale technique provides thermal conductivity measurements from the Cu-ion beam displacement damaged region. We find the thermal conductivity of W damaged to 0.2dpa at room temperature drops from the un-irradiated value of 182 ± 3.3W/mK to 53 ± 8W/mK.http://www.sciencedirect.com/science/article/pii/S2352179116301053 |
| spellingShingle | G.R. Tynan R.P. Doerner J. Barton R. Chen S. Cui M. Simmonds Y. Wang J.S. Weaver N. Mara S. Pathak Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten Nuclear Materials and Energy |
| title | Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten |
| title_full | Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten |
| title_fullStr | Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten |
| title_full_unstemmed | Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten |
| title_short | Deuterium retention and thermal conductivity in ion-beam displacement-damaged tungsten |
| title_sort | deuterium retention and thermal conductivity in ion beam displacement damaged tungsten |
| url | http://www.sciencedirect.com/science/article/pii/S2352179116301053 |
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