Annealing effects on deuterium retention behavior in damaged tungsten
Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tungsten (W) were studied. The D2 TDS spectra as a function of heating temperature for 0.1dpa damaged W showed that the D retention was clearly decreased as the annealing temperature was increased. In p...
| Main Authors: | , , , , , , , , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2016-12-01
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| Series: | Nuclear Materials and Energy |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179115301071 |
| _version_ | 1828200001721860096 |
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| author | S. Sakurada K. Yuyama Y. Uemura H. Fujita C. Hu T. Toyama N. Yoshida T. Hinoki S. Kondo M. Shimada D. Buchenauer T. Chikada Y. Oya |
| author_facet | S. Sakurada K. Yuyama Y. Uemura H. Fujita C. Hu T. Toyama N. Yoshida T. Hinoki S. Kondo M. Shimada D. Buchenauer T. Chikada Y. Oya |
| author_sort | S. Sakurada |
| collection | DOAJ |
| description | Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tungsten (W) were studied. The D2 TDS spectra as a function of heating temperature for 0.1dpa damaged W showed that the D retention was clearly decreased as the annealing temperature was increased. In particular, the desorption of D trapped by voids was largely reduced by annealing at 1173K. The TEM observation indicated that the size of dislocation loops was clearly grown, and its density was decreased by the annealing above 573K. After annealing at 1173K, almost all the dislocation loops were recovered. The results of positron annihilation spectroscopy suggested that the density of vacancy-type defects such as voids, was decreased as the annealing temperature was increased, while its size was increased, indicating that the D retention was reduced by the recovery of the voids. Furthermore, it was found that the desorption temperature of D trapped by the voids for damaged W above 0.3dpa was shifted toward higher temperature side. These results lead to a conclusion that the D retention behavior is controlled by defect density. The D retention in the samples annealed during irradiation was less than that annealed after irradiation. This result shows that defects would be quickly annihilated before stabilization by annealing during irradiation. |
| first_indexed | 2024-04-12T11:06:16Z |
| format | Article |
| id | doaj.art-f8391f98e86349d288d2a2ebcea44849 |
| institution | Directory Open Access Journal |
| issn | 2352-1791 |
| language | English |
| last_indexed | 2024-04-12T11:06:16Z |
| publishDate | 2016-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Materials and Energy |
| spelling | doaj.art-f8391f98e86349d288d2a2ebcea448492022-12-22T03:35:46ZengElsevierNuclear Materials and Energy2352-17912016-12-019C14114410.1016/j.nme.2016.06.012Annealing effects on deuterium retention behavior in damaged tungstenS. Sakurada0K. Yuyama1Y. Uemura2H. Fujita3C. Hu4T. Toyama5N. Yoshida6T. Hinoki7S. Kondo8M. Shimada9D. Buchenauer10T. Chikada11Y. Oya12Graduate School of Science & Technology, Shizuoka University, Shizuoka, JapanGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanInstitute for Materials Research, Tohoku University, Ibaraki, JapanInsitute for Applied Mechanics, Kyushu University, Fukuoka, JapanInsitute of Advanced Energy, Kyoto University, Kyoto, JapanInsitute of Advanced Energy, Kyoto University, Kyoto, JapanFusion Safety Program, Idaho National Laboratory, Idaho, USAHydrogen and Combustion Technology Department, Sandia National Laboratories, Livermore, USAGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanGraduate School of Science & Technology, Shizuoka University, Shizuoka, JapanEffects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tungsten (W) were studied. The D2 TDS spectra as a function of heating temperature for 0.1dpa damaged W showed that the D retention was clearly decreased as the annealing temperature was increased. In particular, the desorption of D trapped by voids was largely reduced by annealing at 1173K. The TEM observation indicated that the size of dislocation loops was clearly grown, and its density was decreased by the annealing above 573K. After annealing at 1173K, almost all the dislocation loops were recovered. The results of positron annihilation spectroscopy suggested that the density of vacancy-type defects such as voids, was decreased as the annealing temperature was increased, while its size was increased, indicating that the D retention was reduced by the recovery of the voids. Furthermore, it was found that the desorption temperature of D trapped by the voids for damaged W above 0.3dpa was shifted toward higher temperature side. These results lead to a conclusion that the D retention behavior is controlled by defect density. The D retention in the samples annealed during irradiation was less than that annealed after irradiation. This result shows that defects would be quickly annihilated before stabilization by annealing during irradiation.http://www.sciencedirect.com/science/article/pii/S2352179115301071Hydrogen isotopes retentionHeavy-ion irradiationAnnealingTDSTEMPAS |
| spellingShingle | S. Sakurada K. Yuyama Y. Uemura H. Fujita C. Hu T. Toyama N. Yoshida T. Hinoki S. Kondo M. Shimada D. Buchenauer T. Chikada Y. Oya Annealing effects on deuterium retention behavior in damaged tungsten Nuclear Materials and Energy Hydrogen isotopes retention Heavy-ion irradiation Annealing TDS TEM PAS |
| title | Annealing effects on deuterium retention behavior in damaged tungsten |
| title_full | Annealing effects on deuterium retention behavior in damaged tungsten |
| title_fullStr | Annealing effects on deuterium retention behavior in damaged tungsten |
| title_full_unstemmed | Annealing effects on deuterium retention behavior in damaged tungsten |
| title_short | Annealing effects on deuterium retention behavior in damaged tungsten |
| title_sort | annealing effects on deuterium retention behavior in damaged tungsten |
| topic | Hydrogen isotopes retention Heavy-ion irradiation Annealing TDS TEM PAS |
| url | http://www.sciencedirect.com/science/article/pii/S2352179115301071 |
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