TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation
Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were...
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| Format: | Article |
| Language: | English |
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Elsevier
2024-04-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323005557 |
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| author | I. Ipatova G. Greaves D. Terentyev M.R. Gilbert Y.-L. Chiu |
| author_facet | I. Ipatova G. Greaves D. Terentyev M.R. Gilbert Y.-L. Chiu |
| author_sort | I. Ipatova |
| collection | DOAJ |
| description | Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 °C) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation.At 1000 °C, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 °C, the faceted helium bubble population was dominated in W. |
| first_indexed | 2024-04-24T17:29:38Z |
| format | Article |
| id | doaj.art-abf874ff2cba4a8da766d2bb2252ac93 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-24T17:29:38Z |
| publishDate | 2024-04-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-abf874ff2cba4a8da766d2bb2252ac932024-03-28T06:37:27ZengElsevierNuclear Engineering and Technology1738-57332024-04-0156414901500TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiationI. Ipatova0G. Greaves1D. Terentyev2M.R. Gilbert3Y.-L. Chiu4Culham Centre for Fusion Energy, United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom; Corresponding author. Culham Centre for Fusion Energy (CCFE), United Kingdom Atomic Energy Authority (UKAEA), Culham Science Centre, Abingdon, OX14 3DB, United Kingdom.School of Computing and Engineering, University of Huddersfield, Huddersfield, HD1 3DH, United KingdomBelgium Nuclear Research Center, NMS unit, Boeretang 200, Mol B2400, BelgiumCulham Centre for Fusion Energy, United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon, OX14 3DB, United KingdomSchool of Metallurgy and Materials, University of Birmingham, Elms Road, Birmingham, B15 2SE, United KingdomHelium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 °C) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation.At 1000 °C, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 °C, the faceted helium bubble population was dominated in W.http://www.sciencedirect.com/science/article/pii/S1738573323005557TungstenZirconium carbidePlasma-facing materialsIn-situ helium exposureFaceted helium bubblesTransmission electron microscopy |
| spellingShingle | I. Ipatova G. Greaves D. Terentyev M.R. Gilbert Y.-L. Chiu TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation Nuclear Engineering and Technology Tungsten Zirconium carbide Plasma-facing materials In-situ helium exposure Faceted helium bubbles Transmission electron microscopy |
| title | TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation |
| title_full | TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation |
| title_fullStr | TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation |
| title_full_unstemmed | TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation |
| title_short | TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation |
| title_sort | tem investigation of helium bubble evolution in tungsten and zrc strengthened tungsten at 800 and 1000°c under 40kev he irradiation |
| topic | Tungsten Zirconium carbide Plasma-facing materials In-situ helium exposure Faceted helium bubbles Transmission electron microscopy |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323005557 |
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