{"title":"高温D+辐照后Be12Ti的氘保留特性和气泡行为","authors":"Yutaka Sugimoto , Mitsutaka Miyamoto , Jae-Hwan Kim , Taehyun Hwang , Suguru Nakano , Masaru Nakamichi , Hiroyasu Tanigawa","doi":"10.1016/j.fusengdes.2025.115220","DOIUrl":null,"url":null,"abstract":"<div><div>In the Japanese demonstration (JA DEMO) fusion reactor, Be<sub>12</sub>Ti blocks as a neutron multiplying material and Li<sub>2</sub>TiO<sub>3</sub> pebbles as a breeding material will be planned to set in the blanket. When the replacement of the blanket due to the life of the structure materials, tritium generation with 200 appm T in Be<sub>12</sub>Ti blocks can be anticipated. The Be<sub>12</sub>Ti blocks containing tritium may cause several problematic issues in JA DEMO. The objective of this study aimed to evaluate the correlation between deuterium (D) retention properties and the bubble behaviors in Be<sub>12</sub>Ti.</div><div>We investigated the D retention properties in the Be<sub>12</sub>Ti samples, which were irradiated with D<sup>+</sup> ions at R.T.-873 K using thermal desorption spectroscopy. The bubble behaviors in the thin Be<sub>12</sub>Ti samples were observed under annealing using in-situ transmission electron microscope (TEM). And the Be samples were prepared to be comparable with Be<sub>12</sub>Ti and done similarly to the same experiment.</div><div>The D desorption peaks were confirmed from the mechanical-polished and electropolished Be<sub>12</sub>Ti samples after irradiation with D<sup>+</sup> at R.T. and high temperature. For both mechanical-polished and electropolished Be<sub>12</sub>Ti samples, the desorption peak shifted to higher temperatures with increasing irradiation temperatures. In-situ TEM observed the bubble behaviors, and Most of the bubbles wouldn’t change in thin Be<sub>12</sub>Ti samples after irradiation with D<sup>+</sup> at R.T. and 673 K during annealing (∼1073 K). These results indicate that no correlation between the deuterium releases and the bubble behavior in Be<sub>12</sub>Ti until 1073 K.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115220"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Deuterium retention properties and bubble behaviors of Be12Ti after irradiation with D+ at high temperature\",\"authors\":\"Yutaka Sugimoto , Mitsutaka Miyamoto , Jae-Hwan Kim , Taehyun Hwang , Suguru Nakano , Masaru Nakamichi , Hiroyasu Tanigawa\",\"doi\":\"10.1016/j.fusengdes.2025.115220\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In the Japanese demonstration (JA DEMO) fusion reactor, Be<sub>12</sub>Ti blocks as a neutron multiplying material and Li<sub>2</sub>TiO<sub>3</sub> pebbles as a breeding material will be planned to set in the blanket. When the replacement of the blanket due to the life of the structure materials, tritium generation with 200 appm T in Be<sub>12</sub>Ti blocks can be anticipated. The Be<sub>12</sub>Ti blocks containing tritium may cause several problematic issues in JA DEMO. The objective of this study aimed to evaluate the correlation between deuterium (D) retention properties and the bubble behaviors in Be<sub>12</sub>Ti.</div><div>We investigated the D retention properties in the Be<sub>12</sub>Ti samples, which were irradiated with D<sup>+</sup> ions at R.T.-873 K using thermal desorption spectroscopy. The bubble behaviors in the thin Be<sub>12</sub>Ti samples were observed under annealing using in-situ transmission electron microscope (TEM). And the Be samples were prepared to be comparable with Be<sub>12</sub>Ti and done similarly to the same experiment.</div><div>The D desorption peaks were confirmed from the mechanical-polished and electropolished Be<sub>12</sub>Ti samples after irradiation with D<sup>+</sup> at R.T. and high temperature. For both mechanical-polished and electropolished Be<sub>12</sub>Ti samples, the desorption peak shifted to higher temperatures with increasing irradiation temperatures. In-situ TEM observed the bubble behaviors, and Most of the bubbles wouldn’t change in thin Be<sub>12</sub>Ti samples after irradiation with D<sup>+</sup> at R.T. and 673 K during annealing (∼1073 K). These results indicate that no correlation between the deuterium releases and the bubble behavior in Be<sub>12</sub>Ti until 1073 K.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"218 \",\"pages\":\"Article 115220\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-26\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625004168\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004168","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
摘要
在日本示范(JA DEMO)聚变反应堆中,Be12Ti块作为中子增殖材料,Li2TiO3鹅卵石作为增殖材料将被计划放置在包层中。由于结构材料寿命的原因,在更换包层时,可预计在Be12Ti块中产生200 appm T的氚。含有氚的Be12Ti块可能会导致JA DEMO中的几个问题。本研究的目的是评估Be12Ti中氘(D)保留性能与气泡行为之间的关系。采用热解吸光谱法研究了D+离子辐照后的Be12Ti样品的D保留特性。利用原位透射电镜(TEM)观察了Be12Ti薄样品在退火条件下的气泡行为。并制备了与Be12Ti相当的Be样品,并进行了类似的实验。经机械抛光和电抛光的Be12Ti样品经高温和高温D+辐照后均有D解吸峰。对于机械抛光和电抛光的Be12Ti样品,随着辐照温度的升高,脱附峰向更高的温度移动。原位透射电镜观察了气泡行为,在高温和673 K (~ 1073 K)下进行D+辐照后,Be12Ti薄样品的气泡大部分没有变化。这些结果表明,在1073 K之前,氘的释放与Be12Ti中的气泡行为没有相关性。
Deuterium retention properties and bubble behaviors of Be12Ti after irradiation with D+ at high temperature
In the Japanese demonstration (JA DEMO) fusion reactor, Be12Ti blocks as a neutron multiplying material and Li2TiO3 pebbles as a breeding material will be planned to set in the blanket. When the replacement of the blanket due to the life of the structure materials, tritium generation with 200 appm T in Be12Ti blocks can be anticipated. The Be12Ti blocks containing tritium may cause several problematic issues in JA DEMO. The objective of this study aimed to evaluate the correlation between deuterium (D) retention properties and the bubble behaviors in Be12Ti.
We investigated the D retention properties in the Be12Ti samples, which were irradiated with D+ ions at R.T.-873 K using thermal desorption spectroscopy. The bubble behaviors in the thin Be12Ti samples were observed under annealing using in-situ transmission electron microscope (TEM). And the Be samples were prepared to be comparable with Be12Ti and done similarly to the same experiment.
The D desorption peaks were confirmed from the mechanical-polished and electropolished Be12Ti samples after irradiation with D+ at R.T. and high temperature. For both mechanical-polished and electropolished Be12Ti samples, the desorption peak shifted to higher temperatures with increasing irradiation temperatures. In-situ TEM observed the bubble behaviors, and Most of the bubbles wouldn’t change in thin Be12Ti samples after irradiation with D+ at R.T. and 673 K during annealing (∼1073 K). These results indicate that no correlation between the deuterium releases and the bubble behavior in Be12Ti until 1073 K.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.