In situ study of defect accumulation in zirconium under heavy ion irradiation
In this study, we report direct observations on heavy ion (Kr2+) irradiation induced changes in microstructures of pure Zr at different temperatures using intermediate voltage electron microscopy. Thin TEM foils were irradiated with 1MeV Kr2+ ions. Materials have been irradiated to different damage...
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| Veröffentlicht in: | Journal of nuclear materials 2013-02, Vol.433 (1-3), p.95-107 |
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| container_title | Journal of nuclear materials |
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| creator | Idrees, Y. Yao, Z. Kirk, M.A. Daymond, M.R. |
| description | In this study, we report direct observations on heavy ion (Kr2+) irradiation induced changes in microstructures of pure Zr at different temperatures using intermediate voltage electron microscopy. Thin TEM foils were irradiated with 1MeV Kr2+ ions. Materials have been irradiated to different damage levels ranging from 0.008dpa to 1dpa at different temperatures ranging from 300°C to 500°C. We particularly concentrate on yield of small defects directly occurring from cascade collapse at very low doses, and their evolution as the dose increases. In situ observation of growth and evolution of these small defects into complex defect structures at high dose has been carried out. Irradiation of materials at different temperatures provided an opportunity to investigate the temperature dependence of defect accumulation in Zr during irradiation. The differences in defect structures, defect densities, and therefore dynamic growth have been discussed in detail as a function of irradiation parameters (dose, temperature). Interaction of irradiation induced defects with existing microstructure and other defects is discussed. |
| doi_str_mv | 10.1016/j.jnucmat.2012.09.014 |
| format | Article |
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Thin TEM foils were irradiated with 1MeV Kr2+ ions. Materials have been irradiated to different damage levels ranging from 0.008dpa to 1dpa at different temperatures ranging from 300°C to 500°C. We particularly concentrate on yield of small defects directly occurring from cascade collapse at very low doses, and their evolution as the dose increases. In situ observation of growth and evolution of these small defects into complex defect structures at high dose has been carried out. Irradiation of materials at different temperatures provided an opportunity to investigate the temperature dependence of defect accumulation in Zr during irradiation. The differences in defect structures, defect densities, and therefore dynamic growth have been discussed in detail as a function of irradiation parameters (dose, temperature). Interaction of irradiation induced defects with existing microstructure and other defects is discussed.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2012.09.014</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Defects ; Density ; Energy ; Energy. 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Thin TEM foils were irradiated with 1MeV Kr2+ ions. Materials have been irradiated to different damage levels ranging from 0.008dpa to 1dpa at different temperatures ranging from 300°C to 500°C. We particularly concentrate on yield of small defects directly occurring from cascade collapse at very low doses, and their evolution as the dose increases. In situ observation of growth and evolution of these small defects into complex defect structures at high dose has been carried out. Irradiation of materials at different temperatures provided an opportunity to investigate the temperature dependence of defect accumulation in Zr during irradiation. The differences in defect structures, defect densities, and therefore dynamic growth have been discussed in detail as a function of irradiation parameters (dose, temperature). Interaction of irradiation induced defects with existing microstructure and other defects is discussed.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Defects</subject><subject>Density</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Evolution</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Foils</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Irradiation</subject><subject>Microstructure</subject><subject>Nuclear fuels</subject><subject>Voltage</subject><subject>Zirconium</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2013</creationdate><recordtype>article</recordtype><recordid>eNqFkE1r3DAQhkVoINs0P6GgS6EXuzOSZa1OpYR-BFJ6yV3I0phqseVUsgLbX18nu_Sa0xzmeefjYew9QouA_adDe0jVz25tBaBowbSA3QXb4V7LptsLeMN2AEI0ElFdsbelHABAGVA79vMu8RLXystaw5EvIw80kl-5877OdXJrXBKPif-N2S8p1pnXFCjz3-SejvylmbML8QV8xy5HNxW6Oddr9vDt68Ptj-b-1_e72y_3je80rs0wjtphtx3fgR56Q86LQWqPigY1GKFUJ5X3vRZmb9ygjTQDkRuHEAI6Ja_Zx9PYx7z8qVRWO8fiaZpcoqUWi0oiyL4H8zoqe4W4l0ZsqDqhPi-lZBrtY46zy0eLYJ9F24M9i7bPoi0Yu32w5T6cV7ji3TRml3ws_8NCQycB9cZ9PnG0mXmKlG3xkZKnEPNm3IYlvrLpH3Q6lto</recordid><startdate>20130201</startdate><enddate>20130201</enddate><creator>Idrees, Y.</creator><creator>Yao, Z.</creator><creator>Kirk, M.A.</creator><creator>Daymond, M.R.</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>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>JG9</scope><scope>L7M</scope></search><sort><creationdate>20130201</creationdate><title>In situ study of defect accumulation in zirconium under heavy ion irradiation</title><author>Idrees, Y. ; Yao, Z. ; Kirk, M.A. ; Daymond, M.R.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c471t-bff7a14101407b69eac2b37c15eb5b9255435cc672989ab7939beeafbddd1a53</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2013</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Defects</topic><topic>Density</topic><topic>Energy</topic><topic>Energy. 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| subjects | Applied sciences Controled nuclear fusion plants Defects Density Energy Energy. Thermal use of fuels Evolution Exact sciences and technology Fission nuclear power plants Foils Fuels Installations for energy generation and conversion: thermal and electrical energy Irradiation Microstructure Nuclear fuels Voltage Zirconium |
| title | In situ study of defect accumulation in zirconium under heavy ion irradiation |
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