用慢正电子束研究H/He中性束辐照W-ZrC合金中的缺陷演化
收稿日期: 2020-05-28
修回日期: 2020-07-21
网络出版日期: 2020-08-13
基金资助
国家自然科学基金项目(11675114)
Defect Evolution in H/He Neutral Beam Irradiated W-ZrC Alloy Using Positron Annihilation Spectroscopy
Received date: 2020-05-28
Revised date: 2020-07-21
Online published: 2020-08-13
Supported by
National Natural Science Foundation of China(11675114)
利用GLADIS中性粒子束辐照设备对W-ZrC (W-0.5%ZrC,质量分数)合金进行纯H中性束辐照、H+6%He (原子分数)中性束辐照。采用Doppler展宽慢正电子束分析(DB-SPBA)和SEM表征样品的空位型缺陷和表面形貌。在相同纯H中性束辐照功率与注量下,Doppler展宽结果表明,辐照表面温度为850℃时,样品中缺陷类型主要为空位与H之比较大的H-V复合体;1000℃的样品不存在缺陷损伤层,这主要是由于缺陷在高温下进行了恢复。SEM结果表明,辐照表面温度为1000℃的样品比850℃的样品表面光滑,表面损伤得到恢复。在相同H+6%He中性束辐照功率与注量下,辐照表面温度为800℃的样品相比700℃的样品,S参数更大,表明辐照表面温度为800℃时,空位型缺陷迁移合并更为明显,空位型缺陷体积更大,样品中的缺陷损伤层更宽,损伤更为严重。
田雪芬 , 刘翔 , 龚敏 , 张培源 , 王康 , 邓爱红 . 用慢正电子束研究H/He中性束辐照W-ZrC合金中的缺陷演化[J]. 金属学报, 2021 , 57(1) : 121 -128 . DOI: 10.11900/0412.1961.2020.00183
Plasma facing materials (PFMs) in future magnetic fusion devices will face various challenges, such as 14.1 MeV neutron and transmutation gas irradiation at high temperatures. W has been considered as one of the most effective candidates for a PFM in recent years. However, pure W exhibits some drawbacks that limit its applications. Conversely, W-ZrC (W-0.5%ZrC, mass fraction) alloy demonstrates excellent performance, such as a relatively low ductile-brittle transition temperature (DBTT), high ductility, and high strength, which will be particularly useful in future fusion reactors. In this work, the Doppler-broadening slow positron beam analysis (DB-SPBA) and SEM were used to characterize the W-ZrC alloy, which had been irradiated by pure H neutral beam or H+6%He (atomic fraction) neutral beam. In the DB-SPBA, parameters S and W were used to characterize the open volume defects in the samples. Under the pure H neutral beam irradiation, the defects were mainly H-V complexes with a large ratio of vacancy to H in the sample at the surface temperature of 850oC. When the surface temperature of the irradiated sample was 1000oC, there was only one kind of vacancy-type defect without any defect damage layer due to the recovery of defect damage in the sample. The surface morphology was smooth and flat at the irradiated sample surface temperature of 1000oC, and the most of pinhole damage structures disappeared compared to the surface temperature of 850oC. The S value in the sample subjected to the H+6%He neutral beam irradiation at the surface temperature of 800oC was larger than that at 700oC because of the increasing vacancy-type defect volume, and defect types were more complex in the 800oC sample. The defect damage layer in the 800oC sample was wider than that in the 700oC sample. Both the 700oC and 800oC samples presented more than one type of defects, but the sample surface damage was significantly more serious at 800oC.
Key words: W-ZrC; H; H/He; positron annihilation
| 1 | Tanabe T, Noda N, Nakamura H. Review of high Z materials for PSI applications [J]. J. Nucl. Mater., 1992, 196-198: 11 |
| 2 | García-Rosales C. Erosion processes in plasma-wall interactions [J]. J. Nucl. Mater., 1994, 211: 202 |
| 3 | Chuyanov V A. ITER EDA project status [J]. J. Nucl. Mater., 1996, 233-237: 4 |
| 4 | Causey R, Wilson K, Venhaus T, et al. Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons [J]. J. Nucl. Mater., 1999, 266-269: 467 |
| 5 | Janeschitz G. Plasma-wall interaction issues in ITER [J]. J. Nucl. Mater. 2001, 290-293: 1 |
| 6 | Wurster S, Gludovatz B, Pippan R. High temperature fracture experiments on tungsten-rhenium alloys [J]. Int. J. Refract. Met. Hard Mater., 2010, 28: 692 |
| 7 | Rieth M, Dafferner B. Limitations of W and W-1% La2O3 for use as structural materials [J]. J. Nucl. Mater., 2005, 342: 20 |
| 8 | Yar M A, Wahlberg S, Bergqvist H, et al. Spark plasma sintering of tungsten-yttrium oxide composites from chemically synthesized nanopowders and microstructural characterization [J]. J. Nucl. Mater., 2011, 412: 227 |
| 9 | Xie Z M, Miao S, Liu R, et al. Recrystallization and thermal shock fatigue resistance of nanoscale ZrC dispersion strengthened W alloys as plasma-facing components in fusion devices [J]. J. Nucl. Mater., 2017, 496: 41 |
| 10 | Kurishita H, Amano Y, Kobayashi S, et al. Development of ultra-fine grained W-TiC and their mechanical properties for fusion applications [J]. J. Nucl. Mater., 2007, 367-370: 1453 |
| 11 | Wang Y K, Miao S, Xie Z M, et al. Thermal stability and mechanical properties of HfC dispersion strengthened W alloys as plasma-facing components in fusion devices [J]. J. Nucl. Mater., 2017, 492: 260 |
| 12 | Xie Z M, Liu R, Miao S, et al. Extraordinary high ductility/strength of the interface designed bulk W-ZrC alloy plate at relatively low temperature [J]. Sci. Rep., 2015, 5: 16014 |
| 13 | Xie Z M, Zhang T, Liu R, et al. Grain growth behavior and mechanical properties of zirconium micro-alloyed and nano-size zirconium carbide dispersion strengthened tungsten alloys [J]. Int. J. Refract. Met. Hard Mater., 2015, 51: 180 |
| 14 | Xie Z M, Liu R, Miao S, et al. High thermal shock resistance of the hot rolled and swaged bulk W-ZrC alloys [J]. J. Nucl. Mater., 2016, 469: 209 |
| 15 | Ding H L, Xie Z M, Fang Q F, et al. Determination of the DBTT of nanoscale ZrC doped W alloys through amplitude-dependent internal friction technique [J]. Mater. Sci. Eng., 2018, A716: 268 |
| 16 | Deng H W, Xie Z M, Wang Y K, et al. Mechanical properties and thermal stability of pure W and W-0.5wt%ZrC alloy manufactured with the same technology [J]. Mater. Sci. Eng., 2018, A715: 117 |
| 17 | Liu R, Xie Z M, Yang J F, et al. Recent progress on the R&D of W-ZrC alloys for plasma facing components in fusion devices [J]. Nucl. Mater. Energy, 2018, 16: 191 |
| 18 | Liu X, Lian Y, Greuner H, et al. Irradiation effects of hydrogen and helium plasma on different grade tungsten materials [J]. Nucl. Mater. Energy, 2017, 12: 1314 |
| 19 | Kajita S, Sakaguchi W, Ohno N, et al. Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions [J]. Nucl. Fusion, 2009, 49: 095005 |
| 20 | Baldwin M J, Doerner R P. Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades [J]. J. Nucl. Mater., 2010, 404: 165 |
| 21 | Baldwin M J, Doerner R P. Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions [J]. Nucl. Fusion, 2008, 48: 035001 |
| 22 | Nishijima D, Ye M Y, Ohno N, et al. Formation mechanism of bubbles and holes on tungsten surface with low-energy and high-flux helium plasma irradiation in NAGDIS-II [J]. J. Nucl. Mater., 2004, 329-323: 1029 |
| 23 | Nishijima D, Ye M Y, Ohno N, et al. Incident ion energy dependence of bubble formation on tungsten surface with low energy and high flux helium plasma irradiation [J]. J. Nucl. Mater., 2003, 313-316: 97 |
| 24 | Tokunaga K, Fujiwara T, Ezato K, et al. Effects of high heat flux hydrogen and helium mixture beam irradiation on surface modification and hydrogen retention in tungsten materials [J]. J. Nucl. Mater., 2009, 390-391: 916 |
| 25 | Miyamoto M, Nishijima D, Baldwin M J, et al. Microscopic damage of tungsten exposed to deuterium-helium mixture plasma in PISCES and its impacts on retention property [J]. J. Nucl. Mater., 2011, 415(): S657 |
| 26 | Wang S J, Chen Z Q, Wang B, et al. Applied Positron Spectroscopy [M]. Wuhan: Hubei Science and Technology Press, 2008: 39 |
| 26 | 王少阶, 陈志权, 王 波等. 应用正电子谱学 [M]. 武汉: 湖北科学技术出版社, 2008: 39 |
| 27 | Yu W Z. Positron Physics and Its Application [M]. Beijing: Science Press, 2002: 441 |
| 27 | 郁伟中. 正电子物理及其应用 [M]. 北京: 科学出版社, 2002: 441 |
| 28 | Van Veen A, Schut H, De Vries J, et al. Analysis of positron profiling data by means of “VEPFIT” [J]. AIP Conf. Proc., 1991, 218: 171 |
| 29 | Greuner H, Maier H, Balden M, et al. Investigation of W components exposed to high thermal and high H/He fluxes [J]. J. Nucl. Mater., 2011, 417: 495 |
| 30 | Jiang B, Wan F R, Geng W T. Strong hydrogen trapping at helium in tungsten: Density functional theory calculations [J]. Phys. Rev., 2010, 81B: 134112 |
| 31 | Iwaoka H, Arita M, Horita Z. Hydrogen diffusion in ultrafine-grained palladium: Roles of dislocations and grain boundaries [J]. Acta Mater., 2016, 107: 168 |
| 32 | Ramachandran R, David C, Magudapathy P, et al. Study of defect complexes and their evolution with temperature in hydrogen and helium irradiated RAFM steel using positron annihilation spectroscopy [J]. Fusion Eng. Des., 2019, 142: 55 |
| 33 | Myers S M, Besenbacher F, N?rskov J K. Immobilization mechanisms for ion‐implanted deuterium in aluminum [J]. J. Appl. Phys., 1985, 58: 1841 |
| 34 | Abramov E, Eliezer D. Hydrogen trapping in helium damaged metals: A theoretical approach [J]. J. Mater. Sci., 1992, 27: 2595 |
/
| 〈 |
|
〉 |