利用氚热活化法制备高标记氧化石墨烯，并将其应用于核电池的光伏电池中

IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Radiochemistry Pub Date : 2024-05-16 DOI:10.1134/s1066362224020073

G. A. Badun, V. A. Bunyaev, M. G. Chernysheva

{"title":"利用氚热活化法制备高标记氧化石墨烯，并将其应用于核电池的光伏电池中","authors":"G. A. Badun, V. A. Bunyaev, M. G. Chernysheva","doi":"10.1134/s1066362224020073","DOIUrl":null,"url":null,"abstract":"<h3 data-test=\"abstract-sub-heading\">Abstract</h3><p>The possibility of tritium introduction into graphene oxide (GO) by tritium thermal activation method was demonstrated. It was established that, in order to produce the highest possible specific radioactivity, thin films of GO with a thickness of 5.6 mg/m<sup>2</sup> must be treated with tritium atoms. The experiment conducted at 77 K showed a number of advantages. GO was processed with tritium atoms, the resulting specific activity of [<sup>3</sup>H]GO reached 2.6 Ci/mg in term of the weight of the initial GO (0.7 Ci/mg after removal of the labile tritium). Specific energy release of [<sup>3</sup>H]GO with this specific activity is 22.3 W/kg, which is quite sufficient for its application as a component of a nuclear battery.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":null,"pages":null},"PeriodicalIF":0.9000,"publicationDate":"2024-05-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Preparation of High-Labeled Graphene Oxide by Tritium Thermal Activation Method for Application in the Betavoltaic Cell of a Nuclear Battery\",\"authors\":\"G. A. Badun, V. A. Bunyaev, M. G. Chernysheva\",\"doi\":\"10.1134/s1066362224020073\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<h3 data-test=\\\"abstract-sub-heading\\\">Abstract</h3><p>The possibility of tritium introduction into graphene oxide (GO) by tritium thermal activation method was demonstrated. It was established that, in order to produce the highest possible specific radioactivity, thin films of GO with a thickness of 5.6 mg/m<sup>2</sup> must be treated with tritium atoms. The experiment conducted at 77 K showed a number of advantages. GO was processed with tritium atoms, the resulting specific activity of [<sup>3</sup>H]GO reached 2.6 Ci/mg in term of the weight of the initial GO (0.7 Ci/mg after removal of the labile tritium). Specific energy release of [<sup>3</sup>H]GO with this specific activity is 22.3 W/kg, which is quite sufficient for its application as a component of a nuclear battery.</p>\",\"PeriodicalId\":747,\"journal\":{\"name\":\"Radiochemistry\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.9000,\"publicationDate\":\"2024-05-16\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Radiochemistry\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1134/s1066362224020073\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"CHEMISTRY, INORGANIC & NUCLEAR\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Radiochemistry","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1134/s1066362224020073","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"CHEMISTRY, INORGANIC & NUCLEAR","Score":null,"Total":0}

引用次数: 0

摘要

摘要通过氚热激活法证明了将氚引入氧化石墨烯（GO）的可能性。实验证明，为了产生尽可能高的比放射性，必须用氚原子处理厚度为 5.6 mg/m2 的氧化石墨烯薄膜。在 77 K 温度下进行的实验显示了许多优点。用氚原子处理 GO 后，[3H]GO 的比放射性活度达到 2.6 Ci/mg（按初始 GO 重量计算）（去除易变氚后为 0.7 Ci/mg）。具有这种比活度的[3H]GO 的比能量释放为 22.3 W/kg，这足以将其用作核电池组件。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

摘要图片

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

Preparation of High-Labeled Graphene Oxide by Tritium Thermal Activation Method for Application in the Betavoltaic Cell of a Nuclear Battery

Abstract

The possibility of tritium introduction into graphene oxide (GO) by tritium thermal activation method was demonstrated. It was established that, in order to produce the highest possible specific radioactivity, thin films of GO with a thickness of 5.6 mg/m² must be treated with tritium atoms. The experiment conducted at 77 K showed a number of advantages. GO was processed with tritium atoms, the resulting specific activity of [³H]GO reached 2.6 Ci/mg in term of the weight of the initial GO (0.7 Ci/mg after removal of the labile tritium). Specific energy release of [³H]GO with this specific activity is 22.3 W/kg, which is quite sufficient for its application as a component of a nuclear battery.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

来源期刊

Radiochemistry CHEMISTRY, INORGANIC & NUCLEAR-

CiteScore

1.30

自引率

33.30%

发文量

期刊介绍： Radiochemistry is a journal that covers the theoretical and applied aspects of radiochemistry, including basic nuclear physical properties of radionuclides; chemistry of radioactive elements and their compounds; the occurrence and behavior of natural and artificial radionuclides in the environment; nuclear fuel cycle; radiochemical analysis methods and devices; production and isolation of radionuclides, synthesis of labeled compounds, new applications of radioactive tracers; radiochemical aspects of nuclear medicine; radiation chemistry and after-effects of nuclear transformations.

期刊最新文献

Neptunium(VI) Nitrate Complexes with Urea and Terpyridine Derivatives Thermal Stability of Irradiated VP-1AP Anion Exchange Resin Development of a Neutron Activation Analysis Method for Studying the Elemental Composition of Atherosclerotic Plaques Hydrogen Peroxide in the Chemistry of f-Elements Disproportionation of Plutonium(V) in EDTA Solutions